The status of Korean nuclear codes and standards

International Nuclear Information System (INIS)

Namha Kim; Jong-Hae Kim

2005-01-01

Korea Electric Power Industry Code (KEPIC), a set of integrated standards applicable to the design, construction and operation of electric power facilities including nuclear power plants, has been developed on the basis of referring to the prevailing U.S. codes and standards which had been applied to the electric power facilities in Korea. Being the developing and managing organization of KEPIC, Korea Electric Association (KEA) published its first edition in 1995, the second in 200,0 and is expected to publish the 2005 edition. KEPIC was applied to the construction of Ulchin Nuclear Units 5 and 6 in 1997, and will be applicable to the construction of forthcoming nuclear power plants in Korea. Along with the effectuation of the Agreement on Technical Barriers to Trade (TBT) in 1995, the international trend related to codes and standards is changing rapidly. The KEA is, therefore, making its utmost efforts so as for KEPIC to keep abreast with the changing environment in international arena. KEA notified ISO/IEC Information Centre of its acceptance of the Code of Good Practice in the Agreement on TBT. The 2005 KEPIC edition will be retrofitted according to the ISO/IEC Guide 21- Adoption of International Standards as regional or national standards. KEA's efforts will help KEPIC correspond with international standards such as ISO/IEC standards, and internationally recognized standards such as ASME codes and standards. (authors)

Strategy. North-Korean nuclear: endgame?

International Nuclear Information System (INIS)

Mirandol, Guylain de

2017-01-01

As North Korea performed new ballistic missile tests in February 2017, and thus violated UN resolutions, this article proposes an overview of the evolutions from nuclear sanctions to economic sanctions. Initially, UN sanctions aimed at struggling against nuclear programmes and proliferation through embargo on arms and materials. After a nuclear test in 2016, South Korea withdrew from a North Korean industrial complex. International sanctions now aim at economically isolating North Korea, at increasing its trade deficit, and at reducing the sending of currencies by North-Korean expatriates. The author notices that these sanctions do not alter manufacturing activities, and that North Korea thus keeps on developing and being integrated into the international division of labour. The last part briefly discusses how North Korea could be able to get around sanctions

Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

International Nuclear Information System (INIS)

Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

2003-04-01

The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

Korean standard of postero-anterior cephalography

Energy Technology Data Exchange (ETDEWEB)

Ahn, Hyung Kyu [College of Dentistry, Seoul National University, Seoul (Korea, Republic of)

1974-11-15

The author conducted an experiment using P-A Cephalography of 242 male and female subjects of ages ranging 2-6, 7- 15, and adult group. By means of Nakago's method of measurement, the standard value of Korean was obtained. The results were as follows; 1. In the group of an age, the male value was slightly greater than female value. 2. In each age group the difference between the right and left widths could be recognizable, however, it was not much great. 3. In each group, regardless of sex, the growth relation was clearly distinguishable at PO, ARI, ARE, MG, AG, and CAW. 4. When the standard value of adult Korean was compared with that of Japanese, that of Japanese was great with respect to the width of maxillary portion and that of Korean was great with respect to the width of mandibular portion. 5. Maximum head width of white man was almost similar to that of Korean, however, maxillary alveolar base width of white man was considerably small or the dental arch was narrow.

Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

International Nuclear Information System (INIS)

Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

2005-04-01

This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility

Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

Energy Technology Data Exchange (ETDEWEB)

Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

2005-04-15

This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility.

Review of the Korean SSAC According to Changes in the Nuclear Environment

International Nuclear Information System (INIS)

Kim, Min Su; Yoon, Wan Ki; Choe, Kwan Kyoo; Jo, Seong Youn; Park, Jae Bum

2005-01-01

Korea has been maintaining efficient and systematic State System for Accounting and Control of nuclear materials (SSAC) for elevation of our nuclear transparency and reliability to international society. So far, Korean SSAC had been considered as a good example of SSAC together with Euratom, Japan, ABACC. But, owing to changing environment such as a series trial due to the KAERI's past nuclear material experiments, strengthened international nonproliferation scheme, advent of integrated safeguards and technology development in nuclear fields, voices of demand for changes in Korean SSAC are being brought up. Therefore, this study grasped and analyzed international nuclear environment and direction of changes in nuclear control regime, besides re-examine the roles of Korean SSAC and proposed the direction where Korean SSAC should be shifted

Register of international standard NP on IT based wireless application in nuclear power plants

International Nuclear Information System (INIS)

Koo, I. S.; Hong, S. B.; Cho, I. W.; Choi, Y. S.; Lee, J. C.

2011-04-01

DC draft of standard technical report for wireless applications in NPP is developed, which is a Korean IT technologies. Wireless technologies are forwardwd to converging technologies nuclear and IT area. These technologies are supported to reduce vulnerability against cyber attacks and are forwarded to international standards which met with the nuclear environment requirements. DC draft of standard technical report is provided and circulated. Korean experts participate in Plenary meeting for IEC TC45/SC45A and intermediate meeting for IEC SC45A/WGA3 and 9. Korean expert takes the chair of wireless session at ANS winter conference. Visible light communication is experimented for feasibility study on reducing vulnerability against cyber attacks. VLC is capable of robust wireless communication against cyber attacks. This is suggested to describe a method for technical report. Issue DTR for wireless applications in NPP in 2012

Study on the Internationalization of Korean Nuclear Journals

International Nuclear Information System (INIS)

Chun, Y. C.; Yoo, J. B.

2006-01-01

This paper is intended to provide some thoughts for a listing of the Korean nuclear journals in the Science Citation Index(SCI), by an analysis of indicators based on the data gathered from relevant literature : Journal of Korean Nuclear Society(JKNS) and Nuclear Engineering and Technology (NET) as cited in the SCI source journal. The study examines as an indicator the number of papers in the JKNS and NET that have been cited by KAERI researchers in the SCI Source Journal (to the end of August 2006). This paper also gives a review of the statistics provided by the Institute for Scientific Information (ISI), as an authoritative source for an evaluation of a global cataloguing of scientific and technical journals, and suggests a view for a listing of the Korean nuclear journals in the SCI by a review of associated selection criteria and methods. It concludes there is a need to increase the number of citations in the SCI source journals of the NET papers to be published from the most recent previous two years

How to realize a nuclear-free Korean peninsula

International Nuclear Information System (INIS)

Yun, Duk-min

1992-01-01

It is certain that, unless the nuclear issue is solved, there can be no progress in inter-Korean relations. To this end, comprehensive and intrusive mutual inspections of any suspicious sites, as well as IAEA inspections, should certainly be implemented. Once international and bilateral arrangements for nuclear inspection are agreed and implemented to the satisfaction of the parties concerned, this will not only solve the problem of nuclear proliferation, but also lay a firm foundation for greater confidence-building measures on the Korean peninsula. This could also be a valuable example for future arms control in Korea. However, even mutual inspection between the two Koreas cannot necessarily guarantee a nuclear-free Korea. The most effective way to ensure the denuclearization of Korea may be to remove elements that the two Koreas perceive as incentives to go nuclear, in parallel with operating a tight and stable verification regime based on mutual and international inspections. Since the major reasons to go nuclear in Korea are military threats and mutual distrust between the two Koreas, no efforts should be spared to rectify these situations. Therefore, confidence- and security-building measures, including full-scale arms control, must be carried out in order to realize and preserve a nuclear-free Korea. In the long run, the greatest contribution to reducing the threat of nuclear proliferation in the Korean peninsula will be through improving overall relations between South and North Korea

Single failure effects of reactor coolant system large bore hydraulic snubbers for Korean Standard Nuclear Power Plant

International Nuclear Information System (INIS)

Choi, T.S.; Park, S.H.; Sung, K.K.; Kim, T.W.; Jheon, J.H.

1996-01-01

A potential snubber single failure is one of the safety significances identified in General Safety Issue 113 for Large Bore Hydraulic Snubber (LBHS) dynamic qualification. This paper investigates dynamic structural effects of single failures of the steam generator and reactor coolant pump snubbers in Korean Standard Nuclear Power Plant by performing the time history dynamic analyses for the reactor coolant system under seismic and postulated pipe break events. The seismic input motions considered are the synthesized ground time histories conforming to SRP 3.7.1, and he postulated pipe break input loadings result from steam generator main seam line and feedwater line pipe breaks which govern pipe breaks remaining after applying LBB to the main coolant line and primary side ranch lines equal to and greater than 12 inch nominal pipe size

Past and future of the Korean national nuclear energy development program

International Nuclear Information System (INIS)

Moon, Joo Hyun

2012-01-01

The Korean government promulgated the 4th Comprehensive Nuclear Energy Promotion Plan (CNEPP) in November 2011, which included the objectives and strategies with the overriding priority that the Korean government and nuclear institutes should carry forward to achieve over next 5 years. Since 1997, when the first CNEPP was promulgated, the Korean government has modified and supplemented the CNEPP every 5 years based on an analysis of the outcomes of the previous CNEPP as well as the outlook on the future nuclear energy uses and developments in domestic and foreign countries. This paper reviews the history of the CNEPP and gives a general idea of the 4th CNEPP. (orig.)

A study on international nuclear organizations and conventions for the globalization of Korean nuclear community

Energy Technology Data Exchange (ETDEWEB)

Lee, Kwang Seok; Oh, Keun Bae; Lee, Byung Wook; Cho, Il Hoon; Lee, Jae Sung; Choi, Young Rok; Ko, Han Seok; Ham, Chul Hoon; Lee, Byung Woon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-12-01

The objective of this study is to analyze the current status of international nuclear organizations and conventions in systems perspective and suggest national strategies for utilizing them for the globalization of Korean nuclear community. This study analyzes the current status of international nuclear organizations such as IAEA(International Atomic Energy Agency) and international nuclear conventions related to nuclear accidents, nuclear liability, physical protection or nuclear safety. Based on the analysis, this study suggests national strategies, in general and specific terms, to utilize international nuclear organizations and conventions for the globalization of Korean nuclear community. Separately from this report this study publishes `IAEA Handbook`, which contains all about IAEA such as statute, membership, organizational structure, main activities, finance and budget, etc.. 9 tabs., 2 figs., 35 refs. (Author).

A study on international nuclear organizations and conventions for the globalization of Korean nuclear community

International Nuclear Information System (INIS)

Lee, Kwang Seok; Oh, Keun Bae; Lee, Byung Wook; Cho, Il Hoon; Lee, Jae Sung; Choi, Young Rok; Ko, Han Seok; Ham, Chul Hoon; Lee, Byung Woon

1995-12-01

The objective of this study is to analyze the current status of international nuclear organizations and conventions in systems perspective and suggest national strategies for utilizing them for the globalization of Korean nuclear community. This study analyzes the current status of international nuclear organizations such as IAEA(International Atomic Energy Agency) and international nuclear conventions related to nuclear accidents, nuclear liability, physical protection or nuclear safety. Based on the analysis, this study suggests national strategies, in general and specific terms, to utilize international nuclear organizations and conventions for the globalization of Korean nuclear community. Separately from this report this study publishes 'IAEA Handbook', which contains all about IAEA such as statute, membership, organizational structure, main activities, finance and budget, etc.. 9 tabs., 2 figs., 35 refs. (Author)

Failure trend analysis for safety related components of Korean standard NPPs

International Nuclear Information System (INIS)

Choi, Sun Yeong; Han, Sang Hoon

2005-01-01

The component reliability data of Korean NPP that reflects the plant specific characteristics is required necessarily for PSA of Korean nuclear power plants. We have performed a project to develop the component reliability database (KIND, Korea Integrated Nuclear Reliability Database) and S/W for database management and component reliability analysis. Based on the system, we have collected the component operation data and failure/repair data during from plant operation date to 2002 for YGN 3, 4 and UCN 3, 4 plants. Recently, we provided the component failure rate data for UCN 3, 4 standard PSA model from the KIND. We evaluated the components that have high-ranking failure rates with the component reliability data from plant operation date to 1998 and 2000 for YGN 3,4 and UCN 3, 4 respectively. We also identified their failure mode that occurred frequently. In this study, we analyze the component failure trend and perform site comparison based on the generic data by using the component reliability data which is extended to 2002 for UCN 3, 4 and YGN 3, 4 respectively. We focus on the major safety related rotating components such as pump, EDG etc

Contrast of Korean industrial standard and overseas standard

International Nuclear Information System (INIS)

Kim, Jong Deuk

2006-12-01

This book introduces Korean Industrial Standard and Overseas Standard, which deals with furniture, plasticizers, valcaning agents, gaskets, steel pipes and tubes. It covers wooden furniture for offices, washing dresser, children crib, chairs and desks for students, chairs and desks made from synthetic resins, tricresyl phosphate, dibutyl phthalate, dioctyl phthalate, phtalic acid dieptil, V packing, vulcanization accelerator CBS(CZ), vulcanization accelerator MBT(M), vulcanization accelerator Zn BDC, steel pipe for heating furnace and carbon steel pope for high voltage piping.

Proceedings of 2nd Korea-China Congress of Nuclear Medicine and the Korean Society Nuclear Medicine Spring Meeting 2000

International Nuclear Information System (INIS)

2000-01-01

This proceedings contains articles of 2nd Korea-China Congress of Nuclear Medicine and 2000 spring meeting of the Korean Society Nuclear Medicine. It was held on May 17-19, 2000 in Seoul, Korean. This proceedings is comprised of 6 sessions. The subject titles of session are as follows: general nuclear medicine, neurology, oncology, radiopharmacy and biology, nuclear cardiology, nuclear cardiology: physics and instrumentation and so on. (Yi, J. H.)

Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon; Kang, Mingyun

2015-01-01

Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately

Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kang, Mingyun [E-Gonggam Co. Ltd., Daejeon (Korea, Republic of)

2015-10-15

Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately.

Applicable approach of the wireless technology for Korean nuclear power plants

International Nuclear Information System (INIS)

Ko, Do Young; Lee, Soo Ill

2013-01-01

Highlights: • To apply wireless technology for Korean NPPs, several stipulations are proposed. • WLAN is proposed as the most appropriate wireless technology for Korean NPPs. • WLAN can be applied to the specific fields except in the control system. • An attitude survey on wireless showed that 94.7% agree with the necessity of wireless. - Abstract: Recently, many nuclear power plants (NPPs) over the world use various types of wireless systems for the advantages. Unfortunately, wireless technologies are not currently installed in any Korean NPPs because it is difficult to solve the negative impact of unexpected outcomes or failures from the influence of the wireless technologies, which is electromagnetic interference and radio-frequency interference (EMI/RFI). Moreover, a lack of desire on the part of Korean nuclear industry to implement it leads to give up benefit from the wireless technologies. To install the wireless technologies with maximum benefit and minimum risk, a systematic approach, which quantify the negative impact and prevent the influence, is essential; therefore, this paper describes an applicable research result on the wireless technology for Korean NPPs based on regulatory guides and current wireless hardware and software technologies. Also, survey on the needs for the wireless technology for Korean nuclear power plants was conducted, because the level of awareness of workers in NPPs regarding wireless technologies is very important issue. In this paper, we propose an applicable system to enhance the applicability for the wireless technology for Korean NPPs. The result based on proposed applicable system shows that wireless local area network (WLAN) is the representative candidate for Korean NPPs, which can be applied to the specific fields of radiation monitoring, voice and data communication, component monitoring and instrumentation, and wireless cameras

Applicable approach of the wireless technology for Korean nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Ko, Do Young, E-mail: kodoyoung@khnp.co.kr; Lee, Soo Ill

2013-12-15

Highlights: • To apply wireless technology for Korean NPPs, several stipulations are proposed. • WLAN is proposed as the most appropriate wireless technology for Korean NPPs. • WLAN can be applied to the specific fields except in the control system. • An attitude survey on wireless showed that 94.7% agree with the necessity of wireless. - Abstract: Recently, many nuclear power plants (NPPs) over the world use various types of wireless systems for the advantages. Unfortunately, wireless technologies are not currently installed in any Korean NPPs because it is difficult to solve the negative impact of unexpected outcomes or failures from the influence of the wireless technologies, which is electromagnetic interference and radio-frequency interference (EMI/RFI). Moreover, a lack of desire on the part of Korean nuclear industry to implement it leads to give up benefit from the wireless technologies. To install the wireless technologies with maximum benefit and minimum risk, a systematic approach, which quantify the negative impact and prevent the influence, is essential; therefore, this paper describes an applicable research result on the wireless technology for Korean NPPs based on regulatory guides and current wireless hardware and software technologies. Also, survey on the needs for the wireless technology for Korean nuclear power plants was conducted, because the level of awareness of workers in NPPs regarding wireless technologies is very important issue. In this paper, we propose an applicable system to enhance the applicability for the wireless technology for Korean NPPs. The result based on proposed applicable system shows that wireless local area network (WLAN) is the representative candidate for Korean NPPs, which can be applied to the specific fields of radiation monitoring, voice and data communication, component monitoring and instrumentation, and wireless cameras.

Introduction of virtual detectors for core monitoring system of korean standard nuclear power plant

International Nuclear Information System (INIS)

Eun, Ki Lee.; Yong, Hee Kim.; Jybe, Ho Cha.; Moon, Ghu Park.

2000-01-01

A novel algorithm known as the virtual detector method (VDM) is introduced to reconstruct the axial power shape (APS) for the on-line core monitoring system of the Korean Standard Nuclear Power Plant (KSNP). A pure statistical method (SM) is also introduced and the results are compared with the currently implemented five-mode Fourier fitting method (FFM). VDM adopts nine virtual detector informations coupled with a regression model based on the Alternating Conditional Expectation (ACE) algorithm. VDM uses Fourier fitting with the information of nine virtual detectors expanded from the currently implemented FFM, which uses five-level detector information. By introducing virtual detectors, we can increase the number of axial detectors, and thus expect the computational errors of APS to be reduced. The two methods (SM and VDM) are applied to in-core mapping data from six cycles of Yong Gwang nuclear power plant Units 3 and 4. For ∼ 3500 cases of APSs extracted from a cycle of operation which is simulated by a three-dimensional nodal code, the accuracy of the three methods (SM, VDM, FFM) is compared. The average root mean square (RMS) error and average of axial peaking error of SM and VDM resulted in reduction of more than 50 % and 70 %, respectively, relative to FFM. VDM and SM also show more realistic axial profiles and predict more accurate axial peaking than FFM. These improvements can contribute to a larger thermal margin. SM shows the most accurate results for all cases. VDM can almost obtain the same results as SM, and using far fewer computation steps. VDM can be a useful tool for precisely reconstructing axial power shapes in a core monitoring system. (authors)

Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 2001

International Nuclear Information System (INIS)

2001-01-01

This proceedings contains articles of 2001 autumn meeting of the Korean Society Nuclear Medicine. It was held on November 16-17, 2001 in Seoul, Korea. This proceedings is comprised of 6 sessions. The subject titles of session are as follows: Cancer, Physics of nuclear medicine, Neurology, Radiopharmacy and biology, Nuclear cardiology, General nuclear medicine. (Yi, J. H.)

Reconstructing the public in old and new governance: a Korean case of nuclear energy policy.

Science.gov (United States)

Kim, Hyomin

2014-04-01

Korean nuclear energy regulatory policies started to change from earlier exclusively technocratic policies into open dialogues after several anti-nuclear protests in the 1990s. However, technocratic policies still coexist with the new regulatory orientation towards openness, participation and institutional accountability. This paper analyzes Korean nuclear regulatory policies since approximately 2005 as a blend of old and new governance. The aim of the paper is not to decide whether new nuclear governance is deliberative or not by completely reviewing Korean nuclear policies after the 2000s. Instead, it provides an empirical account of how seemingly more participatory processes in decision-making entail new problems while they work with and reproduce social assumptions of different groups of the public.

Major NSSS design features of the Korean next generation reactor

International Nuclear Information System (INIS)

Kim, Insk; Kim, Dong-Su

1999-01-01

In order to meet national needs for increasing electric power generation in the Republic of Korea in the 2000s, the Korean nuclear development group (KNDG) is developing a standardized evolutionary advanced light water reactor (ALWR), the Korean Next Generation Reactor (KNGR). It is an advanced version of the successful Korean Standard Nuclear Power Plant (KSNP) design, which meets utility needs for safety enhancement, performance improvement and ease of operation and maintenance. The KNGR design starts fro the proven design concept of the currently operating KSNPs with uprated power and advanced design features required by the utility. The KNGR design is currently in the final stage of the basic design, and the paper describes the major nuclear steam supply system (NSSS) design features of the KNGR together with introduction of the KNGR development program. (author)

Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 2002

International Nuclear Information System (INIS)

2002-01-01

This proceedings contains articles of 2002 autumn meeting of the Korean Society Nuclear Medicine. It was held on November 15-16, 2002 in Seoul, Korea. This proceedings is comprised of 5 sessions. The subject titles of session are as follows: Cancer, Physics of nuclear medicine, Neurology, Radiopharmacy and biology, General nuclear medicine. (Yi, J. H.)

Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 1998

International Nuclear Information System (INIS)

1998-01-01

This proceedings contains articles of 1998 Autumn meeting of the Korean Society Nuclear Medicine. It was held on November 13-14, 1998 in Seoul, Korea. This proceedings is comprised of 5 sessions. The subject titles of session are as follows: general nuclear medicine, neurology, radiopharmacy and biology, nuclear cardiology, physics and instrumentation. (Yi, J. H.)

Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 1997

International Nuclear Information System (INIS)

1997-01-01

This proceedings contains articles of 1997 autumn meeting of the Korean Society Nuclear Medicine. It was held on November 21, 1997 in Kwangju, Korea. This proceedings is comprised of 5 sessions. The subject titles of session are as follows: general nuclear medicine, neurology, radiopharmacy and biology, nuclear cardiology, physics and instrumentation. (Yi, J. H.)

Gap study on technical standards and quality assurance between ITER and Korean regulation

Energy Technology Data Exchange (ETDEWEB)

Kang, Myoung-suk [Kyung Hee University, Yongin-si 446-701, Gyeonggi-do (Korea, Republic of); Lee, Sangil; Lee, Hyoen Gon [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Yongin-si 446-701, Gyeonggi-do (Korea, Republic of)

2016-11-01

Highlights: • This paper is to secure knowledge and expand domestic specialists for license and regulation of future fusion facilities including K-DEMO. - Abstract: Currently, Korea Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project or the ITER Korea has been conducting follow-up surveys and development researches for the core technologies of its non-procurement items. This eventually aims to secure implicit as well as explicit knowledge and expand domestic specialists for future fusion facilities including K-DEMO. As a part of the project, the comparative analysis and gap study of technical standards and Quality Assurance (QA) system between ITER and Korean nuclear facilities are being performed. The goal of this study is to present a roadmap re-systematizing current safety-related standards for the fission-based facilities into fusion-based facilities in Republic of Korea. The research is considering two different tracks. First one is to secure the state-of-the-art of the fusion technical standards continually updated. For its investigation, we organized the Korean fusion safety advisory group that consists of experts from institutes, industries, and universities. The latest information of technical standards have been gathered and updated from each area of expert in periodic manner. The information is classified into Product Breakdown Structure (PBS) including safety classification, major safety issues, analysis computer codes, etc. This task will be re-organized this year such that the technical standards for procurement as well as non-procurement items can be accumulated in systematic and sustainable manner. Second one, called “Gap Study,” is to compare the requirements for domestic nuclear facilities and the results from the first track on the basis of experts’ opinion from the national and private sectors and to recommend the approaches to overcome technical and administrative barriers. The result is

Gap study on technical standards and quality assurance between ITER and Korean regulation

International Nuclear Information System (INIS)

Kang, Myoung-suk; Lee, Sangil; Lee, Hyoen Gon; Heo, Gyunyoung

2016-01-01

Highlights: • This paper is to secure knowledge and expand domestic specialists for license and regulation of future fusion facilities including K-DEMO. - Abstract: Currently, Korea Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project or the ITER Korea has been conducting follow-up surveys and development researches for the core technologies of its non-procurement items. This eventually aims to secure implicit as well as explicit knowledge and expand domestic specialists for future fusion facilities including K-DEMO. As a part of the project, the comparative analysis and gap study of technical standards and Quality Assurance (QA) system between ITER and Korean nuclear facilities are being performed. The goal of this study is to present a roadmap re-systematizing current safety-related standards for the fission-based facilities into fusion-based facilities in Republic of Korea. The research is considering two different tracks. First one is to secure the state-of-the-art of the fusion technical standards continually updated. For its investigation, we organized the Korean fusion safety advisory group that consists of experts from institutes, industries, and universities. The latest information of technical standards have been gathered and updated from each area of expert in periodic manner. The information is classified into Product Breakdown Structure (PBS) including safety classification, major safety issues, analysis computer codes, etc. This task will be re-organized this year such that the technical standards for procurement as well as non-procurement items can be accumulated in systematic and sustainable manner. Second one, called “Gap Study,” is to compare the requirements for domestic nuclear facilities and the results from the first track on the basis of experts’ opinion from the national and private sectors and to recommend the approaches to overcome technical and administrative barriers. The result is

Korean nuclear reactor strategy for the early 21st century

International Nuclear Information System (INIS)

Lee, Byong Whi; Shin, Young Kyun

1991-01-01

The system analysis for Korean nuclear power reactor option is made on the basis of reliability, cost minimization, finite uranium resource availability and nuclear engineering manpower supply constraints. The reference reactor scenarios are developed considering the future electricity demand, nuclear share, current nuclear power plant standardization program and manufacturing capacity. The levelized power generation cost, uranium requirement and nuclear engineering professionals demand are estimated for each reference reactor scenarios and nuclear fuel cycle options from the year 1990 up to the year 2030. Based on the outcomes of the analysis, uranium resource utilization, reliability and nuclear engineering manpower requirements are sensitive to the nuclear reactor strategy and associated fuel cycle whereas the system cost is not. APWR, CANDU: FBR strategy is to be the best option for Korea. However, APWR, CANDU: Passive Safe Reactor (PSR) vFBR strategy should be also considered as a contingency for growing national concerns on nuclear safety and public acceptance deterioration in the future. FBR development and establishment of related fuel cycle should be started as soon as possible considering the uranium shortage anticipated between 2007 and 2032. It should be noted that the increasing use of nuclear energy to minimize the greenhouse effects in the early 21st century would accelerate the uranium resource depletion. The study also concludes that the current level of nuclear engineering professionals employment is not sufficient until 2010 for the establishment of nuclear infrastructure. (Author)

The Impact of the North Korean Nuclear Crisis on Northeast Asia

National Research Council Canada - National Science Library

Han, Jonghun

2007-01-01

The DPRK's nuclear issue is difficult to be managed in a peaceful way because of the negative aspects of nuclear proliferation, unacceptable not only on the Korean Peninsula but also in the international community. North Korea, the U.S...

The role of nuclear energy system for Korean long-term energy supply strategy

International Nuclear Information System (INIS)

Chae, K.N.; Lee, D.G.; Lim, C.Y.; Lee, B.W.

1995-01-01

The energy supply optimization model MESSAGE-III is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Emphasis is placed on the potential contribution of nuclear energy in case of environmental constraints and energy resource limitation. The time horizon is 1993-2040. A program to forecast useful energy demand is developed, and optimization is performed from the overall energy system to the nuclear energy system. Reactor and fuel cycle strategy and the expanded utilization options for nuclear energy system are suggested. FBRs, HTGRs and thorium fuel cycle would play key roles in the long run. The most important factors for nuclear energy in Korean energy supply strategy would be the availability of fossil fuels, CO 2 reduction regulation, and the supply capability of nuclear energy. (author)

Proceedings of the Korean Society Nuclear Medicine Spring Meeting 2002

International Nuclear Information System (INIS)

2002-01-01

This proceedings contains articles of 2002 Spring meeting of the Korean Society Nuclear Medicine. It was held on May 17, 2002 in Suwon, Korea. This proceedings is comprised of 3 sessions. The subject titles of session are as follows: Gynecological and Colorectal cancer, Lung cancer and Lymphoma, and general nuclear medicine. (Yi, J. H.)

Design of Korean nuclear reliability data-base network using a two-stage Bayesian concept

International Nuclear Information System (INIS)

Kim, T.W.; Jeong, K.S.; Chae, S.K.

1987-01-01

In an analysis of probabilistic risk, safety, and reliability of a nuclear power plant, the reliability data base (DB) must be established first. As the importance of the reliability data base increases, event reporting systems such as the US Nuclear Regulatory Commission's Licensee Event Report and the International Atomic Energy Agency's Incident Reporting System have been developed. In Korea, however, the systematic reliability data base is not yet available. Therefore, foreign data bases have been directly quoted in reliability analyses of Korean plants. In order to develop a reliability data base for Korean plants, the problem is which methodology is to be used, and the application limits of the selected method must be solved and clarified. After starting the commercial operation of Korea Nuclear Unit-1 (KNU-1) in 1978, six nuclear power plants have begun operation. Of these, only KNU-3 is a Canada Deuterium Uranium pressurized heavy-water reactor, and the others are all pressurized water reactors. This paper describes the proposed reliability data-base network (KNRDS) for Korean nuclear power plants in the context of two-stage Bayesian (TSB) procedure of Kaplan. It describes the concept of TSB to obtain the Korean-specific plant reliability data base, which is updated with the incorporation of both the reported generic reliability data and the operation experiences of similar plants

Status of the Korean nuclear hydrogen production project

International Nuclear Information System (INIS)

Jonghwa, Chang; Won-Jae, Lee

2010-01-01

The rapid climate changes and the heavy reliance on imported fuel in Korea have motivated interest in the hydrogen economy. The Korean government has set up a long-term vision for transition to the hydrogen economy. To meet the expected demand of hydrogen as a fuel, hydrogen production using nuclear energy was also discussed. Recently the Korean Atomic Energy Committee has approved nuclear hydrogen production development and demonstration which will lead to commercialisation in late 2030's. An extensive research and development programme for the production of hydrogen using nuclear power has been underway since 2004 in Korea. During the first three years, a technological area was identified for the economic and efficient production of hydrogen using a VHTR. A pre-conceptual design of the commercial nuclear hydrogen production plant was also performed. As a result, the key technology area in the core design, the hydrogen production process, the coupling between reactor and chemical side, and the coated fuel were identified. During last three years, research activities have been focused on the key technology areas. A nuclear hydrogen production demonstration plant (NHDD) consisting of a 200 MWth capacity VHTR and five trains of water-splitting plants was proposed for demonstration of the performance and the economics of nuclear hydrogen. The computer tools for the VHTR and the water-splitting process were created and validated to some extent. The TRISO-coated particle fuel was fabricated and qualified. The properties of high temperature materials, including nuclear graphite, were studied. The sulphur-iodine thermochemical process was proved on a 3 litre/ hour scale. A small gas loop with practical pressure and temperature with the secondary sulphur acid loop was successfully built and commissioned. The results of the first phase research increased the confidence in the nuclear hydrogen technology. From 2009, the government decided to support further key technology

Development of new NSSS thermal-hydraulic model for Korean standard nuclear power plant(UCN-3/4) simulator

International Nuclear Information System (INIS)

Kim, Kyung Doo; Jeong, Jae Jun

2001-09-01

The NSSS thermal-hydraulic programs installed in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually adopt very simplified physical models for a real-time simulation of NSSS thermal-hydraulic phenomena, which entails inaccurate results and the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, we developed a realistic NSSS T/H program (named 'ARTS-UCN' code) for the improvement of the Korean Standard Nuclear Power Plant full-scope simulator. ARTS Code, developed as an NSSS T/H model for the KNPEC no. 2 simulator using the RETRAN03 code, was selected as a reference code for ARTS-UCN code development. For the development of ARTS, the followings have been performed: - Improvement of the robustness of RETRAN - Improvement of the real-time simulation capability of RETRAN - Optimum input data generation for the NSSS simulation - New model development that cannot be efficiently modeled by RETRAN - Assessment of the ARTS code. The systematic assessment of ARTS has been conducted in both personal computers (Windows 98, Visual fortran) and the simulator development environment (Windows NT, GSE simulator development tool). The results were resonable in terms of accuracy, real-time simulation and robustness

The role of research in nuclear regulation: A Korean perspective

International Nuclear Information System (INIS)

Yoon, Won-Hyo

1997-01-01

Korea has carried out a very ambitious nuclear power program since the 1970's as part of the nation's industrialization policy. Ever since, Korea has also maintained a strong commitment to nuclear power development as an integral part of the national energy policy which aims at reducing external vulnerability and ensuring against a global fossil fuel shortage. The introduction of nuclear power into Korea has progressed through three stages: the first was a turn-key package supplied by the manufacturer; the second involved a major contractor who was responsible for project management, and design and construction was contracted out, with Korean industry becoming more involved; the third stage has seen Korean industries involved as main contractors based on experience gained from earlier plants. The success of Korea's nuclear power program depends in large part on how to insure safety. Safety has the highest priority in nuclear energy development. Public acceptance has been the most critical problem faced by the nuclear industry in Korea. The public demands the highest level of safety all through the design, construction, and operation of nuclear power plants. Korea has learned that a nuclear plant designed with well addressed safety, implementation of a well grounded QA program during construction, and operated with a proven record of safety, are the only ways to earn public support. Competent and efficient regulation with a strong safety culture and openness in all issues is the most desirable image for regulators to strive for. Korea established a ten year R ampersand D program to obtain self-reliance in nuclear technology and international competitiveness by the early 2000's in 1992. It has actively participated in coordinated research programs in safety issues with bodies including the USNRC, AECB of Canada, IAEA, and OECD/NEA

Korean views on needs for international cooperation in development and development of advanced nuclear power systems

International Nuclear Information System (INIS)

Yoon, Young Ku; Lee, Byong Whi; Shim, Chang Saeng.

1993-01-01

Korea methodology and experience in international cooperation in the field of construction and operation of nuclear power plants as well as Korean views on development and deployment of advanced nuclear nuclear power systems are presented

A study on the direction for the development of the Korean nuclear R and D system toward the globalization

Energy Technology Data Exchange (ETDEWEB)

Won, Byung Chul; Jeong, Yeun Ho; Kim, Myung Ro [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kim, Young Pyung [Korea Univ., Seoul (Korea, Republic of)

1996-02-01

The purpose of this study is to explore future directions for the development of the Korean nuclear research system by comparing the nuclear R and D systems in the U.S., France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed the characteristics of the nuclear research systems in advanced nations in the following areas; 1. configuration of nuclear R and D, 2. morphological characteristics of major nuclear R and D organization, 3. evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and 4. inter-organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the U.S., France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 21 tabs., 11 figs., 36 refs. (Author).

A study on the direction for the development of the Korean nuclear R and D system toward the globalization

International Nuclear Information System (INIS)

Won, Byung Chul; Chung, Yun Ho; Kim, Myung Ro

1994-12-01

This study explores future directions for the development of the Korean nuclear R and D system by comparing the nuclear R and D systems in the US, France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed characteristics of the nuclear R and D systems in advanced nations in the following areas; (1) configuration of nuclear R and D, (2) morphological characteristics of major nuclear R and D organization, (3) evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and (4) inter- organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the US, France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 23 tabs., 4 figs., 34 refs. (Author)

A study on the direction for the development of the Korean nuclear R and D system toward the globalization

International Nuclear Information System (INIS)

Won, Byung Chul; Jeong, Yeun Ho; Kim, Myung Ro; Kim, Young Pyung

1996-02-01

The purpose of this study is to explore future directions for the development of the Korean nuclear research system by comparing the nuclear R and D systems in the U.S., France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed the characteristics of the nuclear research systems in advanced nations in the following areas; 1. configuration of nuclear R and D, 2. morphological characteristics of major nuclear R and D organization, 3. evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and 4. inter-organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the U.S., France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 21 tabs., 11 figs., 36 refs. (Author)

A study on the direction for the development of the Korean nuclear R and D system toward the globalization

Energy Technology Data Exchange (ETDEWEB)

Won, Byung Chul; Chung, Yun Ho; Kim, Myung Ro [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-12-01

This study explores future directions for the development of the Korean nuclear R and D system by comparing the nuclear R and D systems in the US, France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed characteristics of the nuclear R and D systems in advanced nations in the following areas; (1) configuration of nuclear R and D, (2) morphological characteristics of major nuclear R and D organization, (3) evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and (4) inter- organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the US, France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 23 tabs., 4 figs., 34 refs. (Author).

Current Status of The Korean Society of Nuclear Medicine

International Nuclear Information System (INIS)

Koh, Chang Soon

1977-01-01

As the application of nuclear medicine to clinics became generalized and it held an important position, the Korean Society of Nuclear Medicine was founded in 1961, and today it has become known as one of the oldest nuclear medicine societies not only to Asian nations but also to other advanced countries all over the world. Now it has 100 or so regular members composed of students of each medicine filed unlike other medical societies. Only nuclear medicine research workers are eligible for its membership. The Korean Society of Nuclear Medicine holds its regular general meeting and symposium twice per annom respectively in addition to occasional group gatherings and provincial lectures on nuclear medicine. With an eye to exchanging information on symposium, research and know-how, KSNM issued its initial magazine in 1967. Every year two editions are published. Year after year the contents of treatises are getting elevated with researches on each field including the early study on morphology-greatly improved both in quality and quantity. Of late, a minute and fixed quantity of various matters by dynamical research and radioimmunoassay of every kind has become visibly active. In particular, since KSNM, unlike other local societies, keeps close and frequent contact with the nuclear medicine researchers of world-wide fame, monographs by eminent scholars of the world are carried in its magazine now internationally and well received in foreign countries. Now the magazine has been improved to such an extent that foreign authors quote its contents. KSNM invited many a foreign scholar with a view to exchanging the knowledge of nuclear medicine. Sponsored by nuclear energy institute, the nuclear medicine symposium held in Seoul in October of 1966 was a success with Dr. Wagner participating, a great scholar of world wide fame: It was the first international symposium ever held in Korea, and the Korea Japan symposium held in Seoul 1971 was attended by all distinguished nuclear

Site-Specific Atmospheric Dispersion Characteristics of Korean Nuclear Power Plant Sites

International Nuclear Information System (INIS)

Han, M. H.; Kim, E. H.; Suh, K. S.; Hwang, W. T.; Choi, Y. G.

2001-01-01

Site-specific atmospheric dispersion characteristics have been analyzed. The northwest and the southwest wind prevail on nuclear sites of Korea. The annual isobaric surface averaged for twenty years around Korean peninsula shows that west wind prevails. The prevailing west wind is profitable in the viewpoint of radiation protection because three of four nuclear sites are located in the east side. Large scale field tracer experiments over nuclear sites have been conducted for the purpose of analyzing the atmospheric dispersion characteristics and validating a real-time atmospheric dispersion and dose assessment system FADAS. To analyze the site-specific atmospheric dispersion characteristics is essential for making effective countermeasures against a nuclear emergency

Status of operation of radionuclides assay system in Korean nuclear power plant

International Nuclear Information System (INIS)

Hwang, K.H.; Lee, K.J.; Jeong, C.W.; Ahn, S.M.

2003-01-01

In Korea, 17 nuclear power plants composed of 13 pressurized water reactors and 4 CANDU reactors are currently in operation. The cumulative amounts of low and intermediate level radioactive waste in nuclear power plant reached 58,718 drums (unit: 200 liter) in 2001. Efforts to construct LILW disposal facility are continued and its first operation is planned in the year 2008. Its first stage capacity is assumed to be 100,000 drums and total capacity will reach to 800,000 drums. Radwaste disposal site selection is an urgent national project at present time. Regulations and guidelines require detailed information about the radioactive waste package and its contents prior to the transport to the disposal sites. The Enforcement Decree of the Korean Atomic Energy Act (articles 234-17) requires the Minister of Science and Technology (MOST) of Korea to establish regulation for the waste acceptance (MOST notice. 1196-10). It requires detailed information about the radioactive waste package and its contents such as activity of radionuclides, total activities, types and characteristics of waste. For the measurement of the concentrations and activities of radionuclides in radwaste drum, a radionuclides assay system is installed at Korean nuclear power plant (KORI site) in 1996. The waste drum can be measured in the vertical direction with eight vertical segments while in the radial direction also with eight segments. Using this measurement method, homogeneous and non-homogeneous waste drum can be measured. Scaling factor methods have been played a dominant role in the determination of the radionuclides concentration in this system. For corrosion product, generic scaling factors were used due to the similarity and better-characterized properties of Korean analyzed data as compared with the worldwide data base of PWR industry. For fission product and TRU nuclides, it is not easy to determine the generic scaling factors. Thus simple model reflecting the operation history of power

Nuclear standardization development study

International Nuclear Information System (INIS)

Pan Jianjun

2010-01-01

Nuclear industry is the important part of national security and national economic development is key area of national new energy supported by government. nuclear standardization is the important force for nuclear industry development, is the fundamental guarantee of nuclear safe production, is the valuable means of China's nuclear industry technology to the world market. Now nuclear standardization faces to the new development opportunity, nuclear standardization should implement strategy in standard system building, foreign standard research, company standard building, and talented people building to meet the requirement of nuclear industry development. (author)

Analysis of Korean Nuclear Fuel Cycle System by Using DANESS Code

International Nuclear Information System (INIS)

Jeong, Chang Joon

2009-08-01

Korean fast reactor scenarios have been analyzed for various kinds of conversion ratio (CR) by the DANESS system dynamic analysis code. The once-through fuel cycle analysis was modeled based on the Korean 'National Energy Basic Plan' up to 2030 and a postulated nuclear demand growth rate until 2150. The fast reactor scenario analysis has been performed for three kinds of conversion ratios such as 0.3, 0.61 and 1.0. Through the calculations, the nuclear reactor deployment scenario, front-end cycle, back-end cycle, and long-term heat load have been investigated. From the once-through results, it is shown that the nuclear power demand would be ∼70 GWe and the total amount of the spent fuel accumulated by 2150 would be ∼168000 t. The fast reactor (FR) scenario analysis results show that the spent fuel inventory and out-pile transuranic element (TRU) can be reduced by increasing the fast reactor conversion ratio. Furthermore, the long-term heat load of spent fuel decreases with increasing the conversion ratio. However, it is known that the deployment of a fast reactor of low conversion ratio does not much reduce the spent fuel and out-pile TRU inventory due to the fast reactor deployment limitation which is related to the availability of TRU

Global Zero and Deterrence Credibility : A Critical Analysis of Obama`s Nuclear Policy and Extended Nuclear Deterrence Credibility on the Korean Peninsula

OpenAIRE

Ganss, Mathias

2012-01-01

This thesis is a qualitative case study analysis of the whether the nuclear policies of President Obama has weakened the U.S. extended nuclear deterrence credibility on the Korean Peninsula. To answer this, the thesis employs two strategies: First, two variables are discussed; a nuclear capabilities-variable; and a nuclear policy-variable. The purpose is to assess the impact the New START treaty has on U.S. nuclear capabilities, and to assess the implications of Obama`s nuclear policy, expres...

Component reliability analysis for development of component reliability DB of Korean standard NPPs

International Nuclear Information System (INIS)

Choi, S. Y.; Han, S. H.; Kim, S. H.

2002-01-01

The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA and Risk Informed Application. We have performed a project to develop the component reliability DB and calculate the component reliability such as failure rate and unavailability. We have collected the component operation data and failure/repair data of Korean standard NPPs. We have analyzed failure data by developing a data analysis method which incorporates the domestic data situation. And then we have compared the reliability results with the generic data for the foreign NPPs

KOREAN STUDENTS' BEHAVIORAL CHANGE TOWARD NUCLEAR POWER GENERATION THROUGH EDUCATION

Directory of Open Access Journals (Sweden)

EUN OK HAN

2014-10-01

Full Text Available As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017, safety (p<0.000, information acquisition (p<0.000, and subjective knowledge (p<0.000, objective knowledge (p<0.000, attitude (p<0.000, and behavior (p<0.000 were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

A study on the food consumption rates for off-site radiological dose assessment around Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Gab Bock; Chung, Yang Geun

2008-01-01

The internal dose by food consumption mostly accounts for radiological dose of public around Nuclear Power Plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commission) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in 2001∼2002. Also, the food consumption rates for maximum individual are re-estimated

Nuclear power in Korea

Energy Technology Data Exchange (ETDEWEB)

Rim, C S [Radioactive Waste Management Centre, Korea Atomic Energy Research Institute, Taejon, Choong-Nam (Korea, Republic of)

1990-07-01

Before addressing the issue of public and utility acceptance of nuclear power in Korea, let me briefly explain the Korean nuclear power program and development plan for a passively safe nuclear power plant in Korea. At present, there are eight PWRs and one CANDU in operation; two PWRs are under construction, and contract negotiations are underway for one more CANDU and two more PWRs, which are scheduled to be completed by 1997,1998 and 1999, respectively. According to a recent forecast for electricity demand in Korea, about fifty additional nuclear power plants with a generating capacity of 1000MWe are required by the year 2030. Until around 2006, Korean standardized nuclear power plants with evolutionary features such as those in the ALWR program are to be built, and a new type of nuclear power plant with passive safety features is expected to be constructed after 2006. The Korean government is making a serious effort to increase public understanding of the safety of nuclear power plants and radioactive waste storage and disposal. In addition, the Korean government has recently introduced a program of benefits for residents near nuclear power plants. By this program, common facilities such as community centers and new roads are constructed, and scholarships are given to the local students. Nuclear power is accepted positively by the utility and reasonably well by the public in Korea.

Nuclear power in Korea

International Nuclear Information System (INIS)

Rim, C.S.

1990-01-01

Before addressing the issue of public and utility acceptance of nuclear power in Korea, let me briefly explain the Korean nuclear power program and development plan for a passively safe nuclear power plant in Korea. At present, there are eight PWRs and one CANDU in operation; two PWRs are under construction, and contract negotiations are underway for one more CANDU and two more PWRs, which are scheduled to be completed by 1997,1998 and 1999, respectively. According to a recent forecast for electricity demand in Korea, about fifty additional nuclear power plants with a generating capacity of 1000MWe are required by the year 2030. Until around 2006, Korean standardized nuclear power plants with evolutionary features such as those in the ALWR program are to be built, and a new type of nuclear power plant with passive safety features is expected to be constructed after 2006. The Korean government is making a serious effort to increase public understanding of the safety of nuclear power plants and radioactive waste storage and disposal. In addition, the Korean government has recently introduced a program of benefits for residents near nuclear power plants. By this program, common facilities such as community centers and new roads are constructed, and scholarships are given to the local students. Nuclear power is accepted positively by the utility and reasonably well by the public in Korea

Nuclear Power Infrastructure Development Program: Korean Education Program

International Nuclear Information System (INIS)

Choi, Sung Yeol; Hwang, Il Soon; Kim, Si Hwan

2009-01-01

Many countries have decided nuclear power for next energy resources as one of the long-term energy supply options. IAEA projected nuclear power expansion up to 2030 reaching between 447 GWe and 691 GWe compared to 370 GWe and 2660 TWh at the end of 2006. Both low and high projection is accompanied with new nuclear power plant constructions respectively 178 and 357, about 11 units per year, and most new construction is in North America, the Far East, Eastern Europe, the Middle East, and Southeast Asia. During the last forty years, thirty three countries have established commercial nuclear power programs but only some of them have developed comprehensive and large scale peaceful nuclear power infrastructure. Although various cooperation and guidance program of nuclear power infrastructure, developing appropriate environment and infrastructure of nuclear power plant is still challenging problems for developing countries launching nuclear power program. With increasing the demand of safety and safeguard from international society, creating appropriate infrastructure becomes essential requirements in national nuclear power program. In the viewpoint of developing countries, without sufficient explanation and proper guidance, infrastructure could be seen only as another barrier in its nuclear power program. The importance of infrastructure development would be obscured by ostensible business and infrastructure program can result in increasing entering barriers to peaceful nuclear power application field without benefits to developing countries and international community. To avoid this situation by providing enough explanation and realistic case example and cooperate with the countries wanting to establish comprehensive nuclear power infrastructure in the peaceful applications, we are creating the education program of infrastructure development with basic guidelines of the IAEA infrastructure series and Korean experiences from least developed country to advanced country

Korean system of export control to support the commercial nuclear transfer to UAE

International Nuclear Information System (INIS)

Cho, Young Ho

2011-01-01

In December 2009, the Republic of Korea won the contract to build 4 1,400 MW nuclear power reactors worth USD 20 billion in the UAE. The states-owned KEPCO will complete the turnkey project to the UAE including design, engineering, construction, nuclear fuel, operations, maintenance and technical support. Since sensitive nuclear technologies convertible to military purpose can be spread by the transfer of commercial nuclear power plant, it is essential prerequisite to implement nuclear export control tenaciously and effectively. About twenty years have passed since the Republic of Korea introduced export control system in domestic laws and regulations. Marking a major historical milestone in 2009 by ranking among global nuclear suppliers, the Korean government made a major step forward in export control framework to support its next nuclear export goal. (orig.)

A preliminary study on the cultural differences between Korean and Japanese organizations in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Lee, Yong Hee [KAERI, Daejeon (Korea, Republic of); Oh, Ingyu [Hanshin Univ., Seoul (Korea, Republic of); Do, Giang [Sol Bridge International School of Business, Daejeon (Korea, Republic of)

2012-10-15

The meltdowns of the Chernobyl and Fukushima I nuclear reactors are fundamentally linked to their organizational characteristics, as they caused severe social and economic disruptions with equally significant environmental and health related impacts. This shows that we have to find practical solutions to reactor safety from various organizational standpoints by introducing a systematic approach to the issue of organizational deficiencies and human errors. We posit that one of the fundamental causes of organizational deficiencies can be derived from an organizational culture. An organizational culture has both formal and informal types. Generally, organizational culture refers to the common beliefs, values, norms, symbols, and language systems that organizational members use when they add meaning to their organizational behavior within their specific organizations. The purpose of this study is threefold. First, we are interested in finding internal contradictions between Korean organizational culture and U.S.-derived organizational safety mechanisms applied to the operation of Korean NPPs (Nuclear Power Plants). We want to discern safety related problems that are thought to have occurred routinely within the parameters of Korean NPPs owing to the use of U.S. safety mechanisms. Second, we compare the Korean and Japanese organizational culture in NPP mainly on safety and comfort cultures in order to cope with the cultural problems. Third, we want to propose an alternative model of safety mechanisms that are more appropriate for Korean organizational culture, using a system dynamic model that we devised based on empirical observations from the NPPs and factors drawn from the extant literature as compared with Japanese organizational culture.

A preliminary study on the cultural differences between Korean and Japanese organizations in nuclear power plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Yong Hee; Oh, Ingyu; Do, Giang

2012-01-01

The meltdowns of the Chernobyl and Fukushima I nuclear reactors are fundamentally linked to their organizational characteristics, as they caused severe social and economic disruptions with equally significant environmental and health related impacts. This shows that we have to find practical solutions to reactor safety from various organizational standpoints by introducing a systematic approach to the issue of organizational deficiencies and human errors. We posit that one of the fundamental causes of organizational deficiencies can be derived from an organizational culture. An organizational culture has both formal and informal types. Generally, organizational culture refers to the common beliefs, values, norms, symbols, and language systems that organizational members use when they add meaning to their organizational behavior within their specific organizations. The purpose of this study is threefold. First, we are interested in finding internal contradictions between Korean organizational culture and U.S.-derived organizational safety mechanisms applied to the operation of Korean NPPs (Nuclear Power Plants). We want to discern safety related problems that are thought to have occurred routinely within the parameters of Korean NPPs owing to the use of U.S. safety mechanisms. Second, we compare the Korean and Japanese organizational culture in NPP mainly on safety and comfort cultures in order to cope with the cultural problems. Third, we want to propose an alternative model of safety mechanisms that are more appropriate for Korean organizational culture, using a system dynamic model that we devised based on empirical observations from the NPPs and factors drawn from the extant literature as compared with Japanese organizational culture

Seismological analysis of the fourth North Korean nuclear test

Science.gov (United States)

Hartmann, Gernot; Gestermann, Nicolai; Ceranna, Lars

2016-04-01

The Democratic People's Republic of Korea has conducted its fourth underground nuclear explosions on 06.01.2016 at 01:30 (UTC). The explosion was clearly detected and located by the seismic network of the International Monitoring System (IMS) of the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Additional seismic stations of international earthquake monitoring networks at regional distances, which are not part of the IMS, are used to precisely estimate the epicenter of the event in the North Hamgyong province (41.38°N / 129.05°E). It is located in the area of the North Korean Punggye-ri nuclear test site, where the verified nuclear tests from 2006, 2009, and 2013 were conducted as well. The analysis of the recorded seismic signals provides the evidence, that the event was originated by an explosive source. The amplitudes as well as the spectral characteristics of the signals were examined. Furthermore, the similarity of the signals with those from the three former nuclear tests suggests very similar source type. The seismograms at the 8,200 km distant IMS station GERES in Germany, for example, show the same P phase signal for all four explosions, differing in the amplitude only. The comparison of the measured amplitudes results in the increasing magnitude with the chronology of the explosions from 2006 (mb 4.2), 2009 (mb 4.8) until 2013 (mb 5.1), whereas the explosion in 2016 had approximately the same magnitude as that one three years before. Derived from the magnitude, a yield of 14 kt TNT equivalents was estimated for both explosions in 2013 and 2016; in 2006 and 2009 yields were 0.7 kt and 5.4 kt, respectively. However, a large inherent uncertainty for these values has to be taken into account. The estimation of the absolute yield of the explosions depends very much on the local geological situation and the degree of decoupling of the explosive from the surrounding rock. Due to the missing corresponding information, reliable magnitude-yield estimation for the

Korean students' behavioral change toward nuclear power generation through education

International Nuclear Information System (INIS)

Han, Eun Ok; Kim, Jae Rok; Choi, Yoon Seok

2014-01-01

As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017), safety (p<0.000), information acquisition (p<0.000), and subjective knowledge (p<0.000), objective knowledge (p<0.000), attitude (p<0.000), and behavior (p<0.000) were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

Korean students' behavioral change toward nuclear power generation through education

Energy Technology Data Exchange (ETDEWEB)

Han, Eun Ok; Kim, Jae Rok; Choi, Yoon Seok [Dept. of Education and Research, Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

2014-10-15

As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017), safety (p<0.000), information acquisition (p<0.000), and subjective knowledge (p<0.000), objective knowledge (p<0.000), attitude (p<0.000), and behavior (p<0.000) were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

A study on associations of Korean sample group for colors applied to the nuclear power plant control room

Energy Technology Data Exchange (ETDEWEB)

Oh, In Seok; Lee, Jung Woon; Lee, Yong Hee; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejeon (Korea); Lee, Dhong Ha [Suwon University, Whasung (Korea)

2002-05-01

Colors are widely used to warn risk levels and to attract attention of the public. Korea Standard Nuclear Reactor Control Room (KSNRCR) also uses several colors to differentiate warnings, priorities, status, borders, and messages based on the HF010 guideline. However the previous studies showed that the general public not engaged in a specific job domain had different associations of colors as regulated in the standards or the guidelines. It is also expected that the general public not engaged in nuclear power plant industry will have different color association system from the color coding system applied to the KSNRCR. So, this study was performed to show whether there is any difference between color association of a sample Korean group and the color meanings specified in the HF010 guideline. The general public not engaged in the nuclear power plant industry have no idea of the color usage in the nuclear control room. So we converted the specific color usage situation into similar but general situations. In questionnaire, we gave subjects the general situation where color coding is appled and alternative colors which were applied to the HF010 guidelines. And we asked the subjects to choose the colors proper to the situation and to rank the colors according to the degree of suitability. A hundred college students participated in the experiment. 10 refs., 7 tabs. (Author)

Third North Korean nuclear test: what is the state of the North's programme?

International Nuclear Information System (INIS)

Sitt, Bernard

2013-02-01

Two months ago, following North Korea's Unha-3 launch, which put a small satellite into orbit, this publication discussed the possibility of a third North Korean nuclear test. As expected, Pyongyang remained true to its traditional policy of provocation. With carefully calculated timing, it carried out a third nuclear test on 12 February, just hours after Barack Obama's State of the Union address, four days before former leader Kim Jong-il's birthday, and on the eve of the investiture of the new South Korean president on the 25 February. Moreover, the North Korean regime is billing this test as a riposte to the new round of sanctions adopted on by the Security Council on 22 January following the Unha-3 launch in December, as it announced on the 24 January. Yet, aside from the associated posturing, this test confirms, if more confirmation were needed, the North's determination to develop an effective nuclear deterrent. The use of the term miniaturisation is certainly in part a propaganda exercise (can actual miniaturisation be achieved after three nuclear tests, one or two of whose success is highly doubtful?). Nonetheless, North Korea has clearly made progress in developing a nuclear weapon and an intercontinental ballistic missile derived from the Taepodong-2, and has promised to carry out further ballistic launches. Without a doubt, even if the North is a long way from possessing what we would consider an operational nuclear capability, its determination has helped it to make progress, and the country shows no signs of wanting to change course. In light of this fact, what can the international community do beyond existing and future sanctions regimes? Doubtless very little. China, which continues to support the North and which has been known in the past to exert influence on Pyongyang, has expressed its firm displeasure as to the North's activities but appears to have no leverage over Kim Jong-un. The Six-Party talks have little chance of being revived, as North

Status of Korean nuclear industry and Romania-Korea cooperation in nuclear field

International Nuclear Information System (INIS)

Myung-Key, Lee

2005-01-01

Current status of electric power in Korea is characterized by the end of August 2004 by a total installed capacity of about 62,000 MW while the total electricity generation is about 342,000 GWh. The installed capacity of nuclear power is 17,716 MW, sharing 29% of total installed capacity and presenting 38% of total electricity generation in Korea. In accordance with the provisions of the Long Term Energy Plan during the past 40 years, the installed capacity in Korea has been drastically increased. In the 1960's, major sources of electricity generation were locally-mined anthracite coal and hydro, but in the 1970's it was the imported oil. However, through diversification policy the dependence of the imported oil has been rapidly reduced and the share of coal , gas and nuclear generation has been steadily increased. According to the long-term power development plan updated last year, which is extended to 2017, the installed capacity in the year 2017 will be about 88,000 MW. At that time nuclear power will become the largest, sharing 30% and the shares of coal and gas fired power will be steadily decreased. Concerning the Nuclear Power Projects, there are four different nuclear power sites along the coast of Korean peninsula, Yonggwang, Kori, Wolsong and Ulchin. In addition to the currently operating 20 nuclear power plants, there are 6 more nuclear power plants under construction at Shin-Wolsong and Shin-Kori sites. Our efforts to enhance the technology, economy and safety of the nuclear power plants will be continuously pursued. Wolsong unclear power units 1, 2, 3 and 4 are CANDU type reactors which are same type as Romanian Cernavoda nuclear power plants. Operational performance, in terms of capacity factor of NPPs, has remained well above the world average and recorded 91.4% last year. Also, last year, the frequency of unplanned trip was 0.6 time per reactor. In 2004, ten NPPs achieved OCTF, which stands for One Cycle Trouble Free in 2004. Wolsong unit 1

Reliability and validity of the Korean standard pattern identification for stroke (K-SPI-Stroke questionnaire

Directory of Open Access Journals (Sweden)

Kang Byoung-Kab

2012-04-01

Full Text Available Abstract Background The present study was conducted to examine the reliability and validity of the ‘Korean Standard Pattern Identification for Stroke (K-SPI-Stroke’, which was developed and evaluated within the context of traditional Korean medicine (TKM. Methods Between September 2006 and December 2010, 2,905 patients from 11 Korean medical hospitals were asked to complete the K-SPI-Stroke questionnaire as a part of project ' Fundamental study for the standardization and objectification of pattern identification in traditional Korean medicine for stroke (SOPI-Stroke. Each patient was independently diagnosed by two TKM physicians from the same site according to one of four patterns, as suggested by the Korea Institute of Oriental Medicine: 1 a Qi deficiency pattern, 2 a Dampness-phlegm pattern, 3 a Yin deficiency pattern, or 4 a Fire-heat pattern. We estimated the internal consistency using Cronbach’s α coefficient, the discriminant validity using the means score of patterns, and the predictive validity using the classification accuracy of the K-SPI-Stroke questionnaire. Results The K-SPI-Stroke questionnaire had satisfactory internal consistency (α = 0.700 and validity, with significant differences in the mean of scores among the four patterns. The overall classification accuracy of this questionnaire was 65.2 %. Conclusion These results suggest that the K-SPI-Stroke questionnaire is a reliable and valid instrument for estimating the severity of the four patterns.

Underestimation of Self-Reported Smoking Prevalence in Korean Adolescents: Evidence from Gold Standard by Combined Method.

Science.gov (United States)

Hwang, Jun Hyun; Kim, Jong Yeon; Lee, Do Hoon; Jung, Hye Gyoun; Park, Soon-Woo

2018-04-05

The objective of this study was to evaluate the validity of self-reported smoking prevalence in Korean adolescents by using an improved gold standard by a combined method. Using a stratified sampling method, we selected 13 schools from among 397 high schools that participated in the 2015 Korean Youth Health Risk Behavior Web-Based Survey (KYRBS). A second survey (repeated self-reporting questionnaire and urinary cotinine test) was conducted on 1058 students who completed the KYRBS. The gold standard of current smoker was defined as those either self-reporting as a smoker in the second survey or having a urinary cotinine concentration ≥50 ng/mL. The current smoking prevalence in the first survey (KYRBS) was 7.9% (boys 16.5% and girls 1.8%), which was lower than the results based on gold standard (11.3% total, boys 21.9% and girls 3.7%). The sensitivity and specificity of self-reported smoking status was 62.5% and 99.0%, respectively. In particular, the sensitivity of girls (43.5%) was lower than that of boys (67.0%). The self-reported smoking prevalence in Korean adolescents was underestimated, particularly among girls. Careful attention should be paid to interpreting adolescents' smoking prevalence, and supplementary surveys or periodic validity tests need to be considered in Asian countries.

Assessment of bone age in prepubertal healthy Korean children: Comparison among the Korean standard bone age chart, Greulich-Pyle method, and Tanner-Whitehouse method

International Nuclear Information System (INIS)

Kim Jeong Rye; Lee, Young Seok; Yu, Jee Suk

2015-01-01

To compare the reliability of the Greulich-Pyle (GP) method, Tanner-Whitehouse 3 (TW3) method and Korean standard bone age chart (KS) in the evaluation of bone age of prepubertal healthy Korean children. Left hand-wrist radiographs of 212 prepubertal healthy Korean children aged 7 to 12 years, obtained for the evaluation of the traumatic injury in emergency department, were analyzed by two observers. Bone age was estimated using the GP method, TW3 method and KS, and was calculated in months. The correlation between bone age measured by each method and chronological age of each child was analyzed using Pearson correlation coefficient, scatterplot. The three methods were compared using one-way analysis of variance. Significant correlations were found between chronological age and bone age estimated by all three methods in whole group and in each gender (R2 ranged from 0.87 to 0.9, p < 0.01). Although bone age estimated by KS was slightly closer to chronological age than those estimated by the GP and TW3 methods, the difference between three methods was not statistically significant (p > 0.01). The KS, GP, and TW3 methods show good reliability in the evaluation of bone age of prepubertal healthy Korean children without significant difference between them. Any are useful for evaluation of bone age in prepubertal healthy Korean children.

Quantification of brain images using Korean standard templates and structural and cytoarchitectonic probabilistic maps

International Nuclear Information System (INIS)

Lee, Jae Sung; Lee, Dong Soo; Kim, Yu Kyeong

2004-01-01

Population based structural and functional maps of the brain provide effective tools for the analysis and interpretation of complex and individually variable brain data. Brain MRI and PET standard templates and statistical probabilistic maps based on image data of Korean normal volunteers have been developed and probabilistic maps based on cytoarchitectonic data have been introduced. A quantification method using these data was developed for the objective assessment of regional intensity in the brain images. Age, gender and ethnic specific anatomical and functional brain templates based on MR and PET images of Korean normal volunteers were developed. Korean structural probabilistic maps for 89 brain regions and cytoarchitectonic probabilistic maps for 13 Brodmann areas were transformed onto the standard templates. Brain FDG PET and SPGR MR images of normal volunteers were spatially normalized onto the template of each modality and gender. Regional uptake of radiotracers in PET and gray matter concentration in MR images were then quantified by averaging (or summing) regional intensities weighted using the probabilistic maps of brain regions. Regionally specific effects of aging on glucose metabolism in cingulate cortex were also examined. Quantification program could generate quantification results for single spatially normalized images per 20 seconds. Glucose metabolism change in cingulate gyrus was regionally specific: ratios of glucose metabolism in the rostral anterior cingulate vs. posterior cingulate and the caudal anterior cingulate vs. posterior cingulate were significantly decreased as the age increased. 'Rostral anterior' / 'posterior' was decreased by 3.1% per decade of age (p -11 , r=0.81) and 'caudal anterior' / 'posterior' was decreased by 1.7% (p -8 , r=0.72). Ethnic specific standard templates and probabilistic maps and quantification program developed in this study will be useful for the analysis of brain image of Korean people since the difference

Quantification of brain images using Korean standard templates and structural and cytoarchitectonic probabilistic maps

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Sung; Lee, Dong Soo; Kim, Yu Kyeong [College of Medicine, Seoul National Univ., Seoul (Korea, Republic of)] [and others

2004-06-01

Population based structural and functional maps of the brain provide effective tools for the analysis and interpretation of complex and individually variable brain data. Brain MRI and PET standard templates and statistical probabilistic maps based on image data of Korean normal volunteers have been developed and probabilistic maps based on cytoarchitectonic data have been introduced. A quantification method using these data was developed for the objective assessment of regional intensity in the brain images. Age, gender and ethnic specific anatomical and functional brain templates based on MR and PET images of Korean normal volunteers were developed. Korean structural probabilistic maps for 89 brain regions and cytoarchitectonic probabilistic maps for 13 Brodmann areas were transformed onto the standard templates. Brain FDG PET and SPGR MR images of normal volunteers were spatially normalized onto the template of each modality and gender. Regional uptake of radiotracers in PET and gray matter concentration in MR images were then quantified by averaging (or summing) regional intensities weighted using the probabilistic maps of brain regions. Regionally specific effects of aging on glucose metabolism in cingulate cortex were also examined. Quantification program could generate quantification results for single spatially normalized images per 20 seconds. Glucose metabolism change in cingulate gyrus was regionally specific: ratios of glucose metabolism in the rostral anterior cingulate vs. posterior cingulate and the caudal anterior cingulate vs. posterior cingulate were significantly decreased as the age increased. 'Rostral anterior' / 'posterior' was decreased by 3.1% per decade of age (p<10{sup -11}, r=0.81) and 'caudal anterior' / 'posterior' was decreased by 1.7% (p<10{sup -8}, r=0.72). Ethnic specific standard templates and probabilistic maps and quantification program developed in this study will be useful for the analysis

Change in Knowledge of Korean Elementary, Middle, and High School Students in the Fundamental Education on the Nuclear Power Generation

Energy Technology Data Exchange (ETDEWEB)

Kim, Jaerok; Lee, Seungkoo; Choi, Yoonseok; Han, Eunok [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

2014-05-15

Nuclear power facilities and policies are based upon their acceptability to local residents and citizens. In Korea, where nuclear power should be consistently used for national energy security and economic growth, it is important to enhance the social acceptability of nuclear power. To do so, it is necessary to relieve the minds of the Korean people and global nuclear power communities regarding safety. However, there is sharp division on the perception of nuclear power safety between the expert group of operators, philosophers, and regulators, and ordinary citizens, local residents, media, and anti-nuclear groups. This study designed an experiment on knowledge change as part of an educational strategy to enhance public understanding and develop extensive bonds of sympathy for nuclear power generation adequate for Korean society. In order to provide fundamental evidence for planning an educational intervention strategy, this study analyzed the knowledge change of elementary, middle, and high school students, who are then expected to impact education of the general population. As a result of conducting a 45 minute-long education on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of objective knowledge (p<0.000) was significantly higher. This indicates that if education for enhancing social acceptance in Korea argued nuclear power should be constantly used, an education effect could be anticipated. Although objective knowledge does not have any direct influence on behavior change, it is an important variable for attitude change, and thus information on objective knowledge should be offered as well. Here, the contents preferred by the education subjects should also be considered.

Change in Knowledge of Korean Elementary, Middle, and High School Students in the Fundamental Education on the Nuclear Power Generation

International Nuclear Information System (INIS)

Kim, Jaerok; Lee, Seungkoo; Choi, Yoonseok; Han, Eunok

2014-01-01

Nuclear power facilities and policies are based upon their acceptability to local residents and citizens. In Korea, where nuclear power should be consistently used for national energy security and economic growth, it is important to enhance the social acceptability of nuclear power. To do so, it is necessary to relieve the minds of the Korean people and global nuclear power communities regarding safety. However, there is sharp division on the perception of nuclear power safety between the expert group of operators, philosophers, and regulators, and ordinary citizens, local residents, media, and anti-nuclear groups. This study designed an experiment on knowledge change as part of an educational strategy to enhance public understanding and develop extensive bonds of sympathy for nuclear power generation adequate for Korean society. In order to provide fundamental evidence for planning an educational intervention strategy, this study analyzed the knowledge change of elementary, middle, and high school students, who are then expected to impact education of the general population. As a result of conducting a 45 minute-long education on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of objective knowledge (p<0.000) was significantly higher. This indicates that if education for enhancing social acceptance in Korea argued nuclear power should be constantly used, an education effect could be anticipated. Although objective knowledge does not have any direct influence on behavior change, it is an important variable for attitude change, and thus information on objective knowledge should be offered as well. Here, the contents preferred by the education subjects should also be considered

Strategic plan for the development of core technologies for the Korean advanced nuclear power reactor for export

International Nuclear Information System (INIS)

Moon, Joo Hyun; Cho, Young Ho

2010-01-01

With the soaring oil price and worsening global warming, nuclear power has attracted considerable attention on a global scale and a new large market of nuclear power plants (NPPs) is expected. The Korean government aims to export up to 10 NPPs by 2012, based on the successful export of 2 NPPs to the UAE in 2009. It is also going to develop a follow-up model of the Advanced Power Reactor (APR) 1400, and join the world's NPP market under the banner of Korea's original reactor type. For this, it promulgated the strategic plan, NuTech 2012, a technology development plan intended for the early acquisition of core technologies for the Korean advanced NPP design and domestic production of the main components in NPP. This paper introduces the strategic plan of NuTech 2012. (orig.)

The Korean Peninsula

International Nuclear Information System (INIS)

Jeon Bu-Guan

1994-01-01

A realistic approach to North-South arms control and disarmament would require a step-by-step formula encompassing measures for political and military confidence building, arms limitation and reduction. The most fundamental and important condition for achieving meaningful results in disarmament talks is securing political and military confidence. The problem which arose on the Korean peninsula originates from relations of North Korea and IAEA. North Korean position poses a serious threat to the Non-proliferation Treaty, in particular to the IAEA Safeguards regime. Nuclear non-proliferation and the ultimate elimination of nuclear weapons are the primary concerns of the post-cold war era. The Government of South Korea hopes that this issue can be solved through dialogue and negotiations

HRD System and Experience in the Korean Nuclear Industry

Energy Technology Data Exchange (ETDEWEB)

Kang, Byoungkook [KHNP Nuclear Power Education Institute, Busan (Korea, Republic of)

2012-03-15

Korea began to nurture its nuclear energy pioneers in the 1950s when the government dispatched personnel in research and policy-making areas to foreign institutions. Then in 1959, KAERI was established and now plays a leading role in nuclear technology R and D. In addition, Korea's first research reactor, TRIGA Mark-II, was built and put into operation in 1962. This paved the way for advancements in operation and technical development of nuclear reactors. In turn, these accomplishments led to the birth of Korea's first commercial reactor, Kori Unit 1, in the 1970s, and HRD in the nuclear industry was put on the right track. However, the Korean nuclear industry remained heavily dependent on nuclear exporting countries such as the US, Canada, and France. Already confident in construction, Korea took the lead in building Kori Units 3 and 4 and Ulchin Units 1 and 2 in the 1980s, but the country was still in need of technological self-reliance. In order to achieve this, Korea proactively launched systematic HRD programs and dispatched nuclear professionals to overseas nuclear facilities to secure individuals competent in the areas of NPP operations, plant design, and major equipment manufacturing. Thanks to its diligent endeavors, Korea's nuclear entities established independent nuclear training institutes in the 1990s and began producing a large number of competent personnel. This allowed the country to ensure not only the best operation and maintenance engineers but also the essential nuclear technology required for plant design and equipment manufacturing. Since the beginning of the 21{sup st} century, Korea has been producing its nuclear personnel on its own and exchanging nuclear training instructors and trainees with other organizations in fields where specialized knowledge is needed. Furthermore, Korea is taking comprehensive nuclear HRD measures in response to the rising demand for human resources that result from ongoing construction of NPPs in

HRD System and Experience in the Korean Nuclear Industry

International Nuclear Information System (INIS)

Kang, Byoungkook

2012-01-01

Korea began to nurture its nuclear energy pioneers in the 1950s when the government dispatched personnel in research and policy-making areas to foreign institutions. Then in 1959, KAERI was established and now plays a leading role in nuclear technology R and D. In addition, Korea's first research reactor, TRIGA Mark-II, was built and put into operation in 1962. This paved the way for advancements in operation and technical development of nuclear reactors. In turn, these accomplishments led to the birth of Korea's first commercial reactor, Kori Unit 1, in the 1970s, and HRD in the nuclear industry was put on the right track. However, the Korean nuclear industry remained heavily dependent on nuclear exporting countries such as the US, Canada, and France. Already confident in construction, Korea took the lead in building Kori Units 3 and 4 and Ulchin Units 1 and 2 in the 1980s, but the country was still in need of technological self-reliance. In order to achieve this, Korea proactively launched systematic HRD programs and dispatched nuclear professionals to overseas nuclear facilities to secure individuals competent in the areas of NPP operations, plant design, and major equipment manufacturing. Thanks to its diligent endeavors, Korea's nuclear entities established independent nuclear training institutes in the 1990s and began producing a large number of competent personnel. This allowed the country to ensure not only the best operation and maintenance engineers but also the essential nuclear technology required for plant design and equipment manufacturing. Since the beginning of the 21 st century, Korea has been producing its nuclear personnel on its own and exchanging nuclear training instructors and trainees with other organizations in fields where specialized knowledge is needed. Furthermore, Korea is taking comprehensive nuclear HRD measures in response to the rising demand for human resources that result from ongoing construction of NPPs in Korea and the UAE

Development of RCM analysis software for Korean nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1999-12-31

A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

Development of RCM analysis software for Korean nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1998-12-31

A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

Decision support for selecting exportable nuclear technology using the analytic hierarchy process: A Korean case

International Nuclear Information System (INIS)

Lee, Deok Joo; Hwang, Jooho

2010-01-01

The Korean government plans to increase strategically focused R and D investment in some promising nuclear technology areas to create export opportunities of technology in a global nuclear market. The purpose of this paper is to present a decision support process for selecting promising nuclear technology with the perspective of exportability by using the AHP based on extensive data gathered from nuclear experts in Korea. In this study, the decision criteria for evaluating the export competitiveness of nuclear technologies were determined, and a hierarchical structure for the decision-making process was systematically developed. Subsequently relative weights of decision criteria were derived using AHP methodology and the export competitiveness of nuclear technology alternatives was quantified to prioritize them. We discuss the implications of our results with a viewpoint toward national nuclear technology policy.

Korean soft weather

International Nuclear Information System (INIS)

Pressburg, A.P.

2007-01-01

In this paper author deals with the development of nuclear weapons in the Korean People Democratic Republic (North Korea), which was crowned in October 2006 with the first successful underground detonation of nuclear charge. The North Korea so walked into the elite club and became de facto the nuclear great power. Nuclear disarmament negotiations with North Korea misfired. Relationships between the North Korea and the Republic of Korea as well as the China are discussed

Korea nuclear exports: Why did the Koreans win the UAE tender? Will Korea achieve its goal of exporting 80 nuclear reactors by 2030?

International Nuclear Information System (INIS)

Berthelemy, Michel; Leveque, Francois

2011-01-01

The success of Korea in winning, in December 2009, a USD 18.6 billion nuclear tender in the United Arab Emirates (UAE) has led to a growing interest in the organization and strengths of the Korean nuclear industry. In this paper, we present the main economic and political factors that explain the success of the Korean consortium. In particular, thanks to an active national program of Nuclear Power Plant (NPP) construction, Korea has developed distinct competitive advantages in terms of low cost, high credibility and high performance. At the same time, due to the important barriers to enter into the nuclear export market in the UAE, Korea has had to sacrifice its profit margin and has benefited from a strong political support from its government through export financing. More importantly, Korea's success is also due to its alliance with Westinghouse and the support of the US diplomacy. Subsequently, we show that while Korea has recently experienced setbacks in nuclear tenders, it will most certainly try to win in the short run a second nuclear tender with another aggressive price. In the longer run, Korea could take a growing share of the international market for NPPs. However, the extent to which Korea can achieve its long term export target will depend upon its capacity to finance nuclear export through export credits and upon the development of its alliance with Westinghouse. It is important to note that this paper was written before the Fukushima nuclear disaster. The scale of the human and environmental consequences of this accident are still unknown, and will undoubtedly have short and long term consequences on nuclear safety requirements and public attitude toward nuclear energy, which will most certainly impact the outlooks for nuclear new-builds. (authors)

Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Yoon, Ji Hyun; Lee, Bong Sang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-08-15

The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made of SA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR 50.61a matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better than did that of Regulatory Guide (RG) 1.99 Rev. 2. This is attributed to the fact that the prediction performance of 10 CFR 50.61a was enhanced by considering the difference in radiation embrittlement sensitivity among the different types of RPV materials.

How the South Korean energy program has been saving the US nuclear industry

International Nuclear Information System (INIS)

Shorrock, T.

1982-01-01

The view is given that the US government financed South Korea's nuclear program at taxpayer expense. Westinghouse Electric Co., which supplied the equipment for Korea's reactors, was said to be the taxpayers' beneficiary. US participation was justified on grounds of commercial benefits to US companies, fuel suppliers, and world prestige as a promoter of peaceful nuclear applications and assistance to developing countries. The Export-Import Bank provided funding after strong urging by the US Embassy in Korea and Westinghouse. The author states that pressure was also put on the Korean government to award contracts to US suppliers. The negotiations have spanned periods of unrest in Korea

Standards development for the nuclear industry

International Nuclear Information System (INIS)

Domondon, D.B.

The ushering of nuclear era in the Philippines with the construction of the PNPP-I (Philippine Nuclear Power Plant) necessitates the evolvement and use of nuclear standards as a tool for safety evaluation in the licensing process. The Department of Nuclear Regulation and Safeguards under the Philippine Atomic Energy Commission has as one of its responsibilities the establishment of regulatory standards to ensure safe operation of nuclear facilities. This article points out the needs for nuclear standards and the steps in standard development which involve an enormous amount of resources in terms of manpower, expertise and money. The staff of the Department of Nuclear Regulations and Safeguards (DNRS) does not intend to engage in the original development of standards; rather, it reviews standards in use elsewhere, specifically in the U.S. and adopts to local conditions. (author)

Social networking-based simulations for nuclear security: Strategy assessment following nuclear cyber terror on South Korean nuclear power plants (NPPs)

International Nuclear Information System (INIS)

Woo, Tae Ho; Kwak, Sang Man

2015-01-01

Highlights: • The cyber terror modeling is made by the social networking algorithm. • This is applicable by the social networking service (SNS). • Security of nuclear industry could be controlled by the network theory. • Newly developed complex algorithm can be introduced. • Simplified graphics show the operator easily. - Abstract: Nuclear energy has been studied for the secure power productions, which is based on the simulation study following the incident of nuclear cyber terror attack on South Korean nuclear power plants (NPPs). The social networking is used for the terror incident modeling and its prevention strategies. The nuclear industry could be investigated in the aspect of minimizing the dangerous situations caused by possible terror attacks which are considered by the society oriented connectivity among the related people or groups. The social networking circle by system dynamics diagram (SNCSD) is constructed, where the configuration of a model social networking example by system dynamics (SD) is applied. From A to H regions, the values are obtained by the random numbers incorporated with the designed algorithms. The results show the comparative values of terror possibilities which are based on the proposed social networking algorithm. It is possible to prepare for potential terrorism in the nuclear industry

Improvement of core monitoring code cecor by the virtual segmentation of the self powered neutron detector loaded at Korean Standard Nuclear Plant

International Nuclear Information System (INIS)

Choi, T.; Jung, Y.S.

2006-01-01

Full text: Full text: Korean Standard Nuclear Plant uses Self Powered Neutron Detectors (SPNDs) to measure the neutron flux in the reactor core. The SPND's height is 40 cm and is located axially at the five different positions and 45 radial places. The design code simulated a reactor core is calculated by segmentation of the core. The segmentation is called as 'node', of which size is normally 20 cm. The axial height of the detector is larger than that of the node, and the larger detector's height maybe product some error on the axially complex shape. The analysis with the detector's signals showed some errors at the non-cosine axial flux shape. In order to reduce the errors for the shape, we tried to divide the detector by introducing the virtual boundary in the detector. Then, each axially 5 detectors had two virtual segmentations respectively and the detector's signal was divided by the inputs. So the more virtual detector's signals were gotten, the more accurate axial shape was produced. The result with virtual segmentations in a detector gave less deviation than the case without virtual segmentation (the current model). After the middle of cycle at the initial core specially, the axial neutron flux shape is changed to the saddle type one. The current model gave some error in Root Mean Square (RMS) between the measured value and the calculated one. The virtual segmentation model gave the better agreement at that time

Quantitative and radiological assessment of PYRO-SFR closed fuel cycle against direct disposal of spent nuclear fuel from Korean nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Khan, Muhammad Minhaj; Lee, Suhong; Cheong, Jaehak; Whang, Jooho [Kyunghee University, Seoul (Korea, Republic of)

2016-12-15

Calculations have been made to estimate the generation of SNF including Plutonium (Pu) and minor actinides (MAs) from PWR and PHWR NPPs by using the IAEA code Nuclear Fuel Cycle Simulation System (NFCSS) for the period of 2016, 2030 as 12 more NPPs will be added by the year 2029. In order to find the optimize option for SNF management through sustainable use of nuclear energy system and reduce the associated radiological risk, 4 scenarios to burnout the Pu and MAs are analyzed. Estimation for the amount of SNF including major radionuclides has made for the year of 2016, 2030, 2089 and 2109 with an approximate amount of 148,19.65MT, 248,34.6 MT, 41572.23 MT and 61272.24 MT of SNF will be generated respectively. Radioactivity and radiotoxicity is calculated in order to access the radiological risk in terms of ingestion. Four Transmutation strategies is predicted to make Korean NPPs sustainable by incorporating KALIMER-600 (Burner) reactor in Korean nuclear fleet with an approximate transmutation rate of 99.77%, 96.57%, 95.34% and 97.58% for MA only (scenario-1), (MA & Pu) scenario-2, scenario-3 (MA only till the year 2125) and scenario-4 MA & Pu till the year 2148) respectively.

Nuclear Option in Korea

International Nuclear Information System (INIS)

Han, K. I.

2002-01-01

With sixteen(16) operating nuclear units in Korea, the share of nuclear power generation reached 41% of the total electric power generation as of December 2000. A prediction is that it would further increase to 44.5% by year 2015 according to the national long term power development plan. Four units are currently under construction with 6 more units in order. With little domestic energy resource and increasing energy demand to support national economic growth, Korea has chosen nuclear power as one of the major energy sources to ensure stable power supply and to promote energy self-sufficiency. It has been recognized that nuclear power in Korea is not a selective option but rather a necessity. The Korean nuclear power development started with construction of a 600 MWe size reactor that was designed and constructed by foreign vendors. As the national grid capacity became larger, the size of nuclear units increased to 1000 MWe class. In the mean time, the need for nuclear technology self-reliance grew not only in operation and maintenance but also in construction, manufacturing and design. For this, a nuclear technology self-reliance program has been embarked with the support of the Government and utility, and the 1000 MWe class KSNP(Korean Standard Nuclear Power Plant) has been developed. The KSNPs are currently being designed, manufactured, constructed and operated by relevant Korean entities themselves. To fit into a larger capacity national grid and also to improve nuclear economic competitiveness, the 1400 MWe class KNGR(Korean Next Generation Reactor) design has been developed uprating the 1000 MWe KSNP design. Its construction project is currently under contract negotiation, and is planned to be finished by 2010. In the mean time, to be ready for future electric power market deregulation, the 600 MWe class small KSNP design is being developed downsizing the KSNP. A modular small size reactor, SMART(System Integrated Modular Advanced Reactor) is also being

Argentine nuclear energy standardization activities

International Nuclear Information System (INIS)

Boero, Norma; Corcuera, Roberto; Palacios, Tulio A.; Hey, Alfredo M.; Berte, G.; Trama, L.

2004-01-01

The International Organization for Standardization (ISO) has more than 200 Technical Committees that develop technical standards. During April 2004 took place in Buenos Aires the 14th Plenary of the ISO/TC 85 Nuclear Energy Committee. During this Plenary issues as Nuclear Terminology, Radiation Protection, Nuclear Fuels, Nuclear Reactors and Irradiation Dosimetry was dealt with. 105 International delegates and 45 National delegates (belonging to CNEA, ARN, NASA, INVAP, CONUAR, IONICS and other organizations) attended the meetings. During this meeting ISO/TC 85 changed its scope; the new scope of the Committee is 'Standardization in the fields of peaceful applications of nuclear energy and of the protection of individuals against all sources of ionizing radiations'. This work summarizes the most important advances and resolutions about the development of standards taken during this meeting as well as the main conclusions. (author) [es

Nuclear performance standards: Promoting efficient generation

International Nuclear Information System (INIS)

Nagelhout, M.

1990-01-01

Nuclear plant performance standards are designed to share the risks of operation associated with nuclear generation. Such standards often shift risks from ratepayers to utility shareholders, even without a finding of imprudence or mismanagement. The rationale underlying nuclear performance standards is that ratepayers should not be responsible for excessive replacement power costs incurred as a result of unreasonable decisions by utility management, especially because the high fixed costs of nuclear plants are already included in base rates. In addition, performance standards can be designed to provide incentives to reward utilities that achieve superior nuclear performance, for the benefit of both ratepayers and shareholders

KoVariome: Korean National Standard Reference Variome database of whole genomes with comprehensive SNV, indel, CNV, and SV analyses.

Science.gov (United States)

Kim, Jungeun; Weber, Jessica A; Jho, Sungwoong; Jang, Jinho; Jun, JeHoon; Cho, Yun Sung; Kim, Hak-Min; Kim, Hyunho; Kim, Yumi; Chung, OkSung; Kim, Chang Geun; Lee, HyeJin; Kim, Byung Chul; Han, Kyudong; Koh, InSong; Chae, Kyun Shik; Lee, Semin; Edwards, Jeremy S; Bhak, Jong

2018-04-04

High-coverage whole-genome sequencing data of a single ethnicity can provide a useful catalogue of population-specific genetic variations, and provides a critical resource that can be used to more accurately identify pathogenic genetic variants. We report a comprehensive analysis of the Korean population, and present the Korean National Standard Reference Variome (KoVariome). As a part of the Korean Personal Genome Project (KPGP), we constructed the KoVariome database using 5.5 terabases of whole genome sequence data from 50 healthy Korean individuals in order to characterize the benign ethnicity-relevant genetic variation present in the Korean population. In total, KoVariome includes 12.7M single-nucleotide variants (SNVs), 1.7M short insertions and deletions (indels), 4K structural variations (SVs), and 3.6K copy number variations (CNVs). Among them, 2.4M (19%) SNVs and 0.4M (24%) indels were identified as novel. We also discovered selective enrichment of 3.8M SNVs and 0.5M indels in Korean individuals, which were used to filter out 1,271 coding-SNVs not originally removed from the 1,000 Genomes Project when prioritizing disease-causing variants. KoVariome health records were used to identify novel disease-causing variants in the Korean population, demonstrating the value of high-quality ethnic variation databases for the accurate interpretation of individual genomes and the precise characterization of genetic variations.

Trace of Korean mechanical industry

International Nuclear Information System (INIS)

1996-12-01

This book reports 50 years of Korean mechanical engineers, which includes birth and history, remembrance and future of Korean society of mechanical engineers, current situation and development of mechanical industry such as national industry and 50 years of mechanical industry, track, airline industry, ship and marine engine, a precision instrument, cutting work, casting, welding, plastic working freeze and air handling nuclear power and textile machinery.

The Korean threat steps up a notch

International Nuclear Information System (INIS)

Chicheportiche, Romain; Thouverez, Pierre

2016-01-01

As North Korea announced a successful test for its first hydrogen nuclear bomb, the author first recalls the origins of the Korean conflict, and then presents the North Korean nuclear weapon programme as a result of a sense of insecurity for the North Korean regime, notably after the collapse of USSR. The nuclear weapon then became a priority and the programme has been rather quickly developed, probably with the help of the father of the Pakistani bomb. A first and second plutonium-based bombs have been tested, and then an enriched uranium-based bomb, and lastly, in January 2016, a hydrogen bomb. Doubts about this achievement are evoked. Then, the author proposes a brief overview of negotiations with the USA, and outlines the problematic behaviour of North Korea regarding the regional situation in an evolving context: a stronger Chinese economy, change in China's position towards North Korea, and Japan re-militarization

Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

International Nuclear Information System (INIS)

Kusnowo, Arlinah; Darmawati, Suzie

2002-01-01

Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

National standards for the nuclear industry

International Nuclear Information System (INIS)

Laing, W.R.; Corbin, L.T.

1981-01-01

Standards needs for the nuclear industry are being met by a number of voluntary organizations, such as ANS, ASTM, AWS, ASME, and IEEE. The American National Standards Institute (ANSI) coordinates these activities and approves completed standards as American National Standards. ASTM has two all-nuclear committees, E-10 and C-26. A C-26 subcommittee, Test Methods, has been active in writing analytical chemistry standards for twelve years. Thirteen have been approved as ANSI standards and others are ready for ballot. Work is continuing in all areas of the nuclear fuel cycle

Future perspectives of human resources in nuclear technology - The Korean case

International Nuclear Information System (INIS)

Min, B.J.

2007-01-01

Full text: Synopsis. The prospects for growth for the nuclear power industry in the Republic of Korea, have improved notably in last few years, as the need for generating capacity grows to meet burgeoning energy demand and developmental needs, and as environment, climate change and energy supply security continue become matters of rising concern. Nuclear technology itself has also changed, with evolutionary and innovative changes in reactor design and safety measures. Nuclear technology development both requires and fosters human resource development (HRD). A continuous, consistent and well-managed programme of HRD is crucial to assure continuity over time in the needed capacities, skills and knowledge, and to establish and maintain a cadre of manpower variously trained in different nuclear-related skills and educated in nuclear relevant fields. It also fosters the development of spin-off industries and synergies. Productive and goal-oriented HRD and M is a dynamic long-term process that balances the dynamics of supply and demand of human resources with respect to the education, recruitment, maintenance and proper training of the human resources needed for industry operations as well as innovation. Such a programme in fact was the foundation for the birth of the Korean nuclear industry, with the government sponsoring nuclear-related- training and education for hundreds of persons under the tutelage of companies and countries overseas having experience with nuclear and related sciences and technology. This cadre, once repatriated, formed the nucleus for domestic training and education programmes as an integral part of nuclear energy development and consistent with national policies. HRD and M in Korea today comprises an educational network among academic and research institutes, government and industry. Forming such a cadre is not the result of a one-off training process, but must be planned and sustained consistently over time and its talents regularly applied

Methods and Effects of Safety Enhancement in Korean PSR

International Nuclear Information System (INIS)

Kim, Young Gab; Park, Jong Woon

2009-01-01

Periodic Safety Review (PSR) is a comprehensive study on a nuclear power plant safety, taking into account aspects such as operational history, ageing, safety analyses and advances in code and standards since the time of construction. In Korea, PSRs have been performed for 20 units and have been effectively used to obtain an overall view of actual plant safety to determine reasonable and practical modifications that should be made in order to obtain a higher level of safety approaching that of modern plants. Among many safety enhancements achieved from Korean PSRs, new safety analyses are the important methods to confirm plant safety by increasing safety margin for specific safety issues. Methods and effects of safety enhancements applied in Korean PSRs are reviewed in this paper in light of new safety analyses to obtain additional safety margins

Recent activities on nuclear codes and standards

International Nuclear Information System (INIS)

Minematsu, Akiyoshi; Ishimoto, Shozaburo; Honjin, Masao

2000-01-01

The technical codes and standards relating to the nuclear power stations in Japan are prepared by shapes of laws (ministerial ordinances and bulletins) issued by the government and obliged to comply with by 'the Law concerning the Regulations of Nuclear Material Substances, Nuclear Fuel Substances and Nuclear Reactors' and 'the Electricity Business Act' and of guides defined by the Nuclear Safety Commission, and further some private standards have been issued at a shape of complement of these laws and guides by receiving national recommendation. On the other hand, in the fields of electricity and heat facilities except atomic energy, simplification and feature stipulation of the national technical codes and standards was recently carried out, by which a system usable for the private standards in and out of Japan were prepared through approval of the private Japan Electrotechnical Standards and Codes Committee (JESC). As the nuclear field was now excepted from simultaneous transfer to the private standard and the standard application system, it is expected in future to realize similar transfer if possible and preparation of the private standards is now being advanced. Here were introduced on present state on technical codes and standards relating to the nuclear power generation facilities and recent trends on their private standardization. (G.K.)

A cytogenetic study of Korean native goat bred in the nuclear power plant using the micronucleus assay

International Nuclear Information System (INIS)

Kang, Chang-Mo; Ji, Young-Hoon; Lee, Hae-June; Kim, Se-Ra; Kim, Jong-Choon; Kim, Sung-Ho

2005-01-01

Cytogenetic and hematological analysis was performed on the peripheral blood lymphocytes (PBLs) obtained from Korean native goats bred in two nuclear power plants (Wolsong and Uljin) and a control area. The frequencies of gamma-ray-induced micronuclei (MN) in the cytokinesis-blocked (CB) lymphocytes at several doses were measured in three Korean native goats. The measurements performed after irradiation showed dose-related increases in the MN frequency in each of the donors. The results were analyzed using a linear-quadratic model with a line of best fit of y=0.1019D+0.0045D 2 +0.0093 (y=number of MN/GB cells and D=irradiation dose in Gy). The MN rates in the goats from the Wolsong and Uljin nuclear power plant, and the control area were 9.60±2.88, 6.83±1.47 and 9.88±4.32 per 1,000 CB lymphocytes, respectively. The apparent difference is not statistically significant. The MN frequencies of PBLs from goats bred in three areas means that the values are within the background variation in this experiment. The MN frequencies and hematological values were similar regardless of whether the goats were bred in the nuclear power plant or the control area. (author)

Technical verification of advanced nuclear fuel for KSNPs

International Nuclear Information System (INIS)

Lee, C. B.; Bang, J. G.; Kim, D. H. and others

2002-03-01

KNFC has developed the advanced 16x16 fuel assembly for the Korean Standard Nuclear Plants through the three-year R and D project (from April 1999 to March 2002) under the Nuclear R and D program by MOST. The purpose of this project is to verify the advanced 16x16 fuel assembly for the Korean Standard Nuclear Plants being developed by KNFC during the same period. Verification tests for the advanced fuel assembly and its components such as characteristic test on the spacer grid spring and dimple, static buckling and dynamic impact test on the 5x5 partial spacer grid, the fuel rod vibration test supported by the PLUS7 mid-spacer grid, fretting wear test, turbulent flow structure test in wind tunnel and corrosion test were performed by using the KAERI facilities. Design reports and test results produced by KNFC were technically reviewed. For the domestic production of burnable poison rod, manufacturing technology of burnable poison pellets was developed

Status of Korean nuclear industry and Romania-Korea cooperation in the field of nuclear power

International Nuclear Information System (INIS)

Lee, Myung Key

2005-01-01

The Kyoto Protocol on climate change has urged the world to explore ways of cutting down the greenhouse emissions, and it also boosted a number of nuclear power projects that is so-called the renaissance of nuclear power. Nuclear power has proven to be the cleanest energy source and one of the cheapest types of energies, compared with other energy sources. Korea began developing its nuclear power projects from the early 1970's. Since the first nuclear power plant Kori Unit 1, started commercial operation in 1978, Korea has continuously promoted the development of nuclear power projects, and today it operates 20 nuclear power units (17,716 MW), including 4 units of CANDU plants. Korea ranked No. 6 in the world in terms of installed capacity of nuclear power plants, and 40% of its domestic electricity generation comes from nuclear power plants. The average plant capacity factor was 95.5% in 2005, which is about 16% than the world average of around 79%. All the Korean nuclear power projects are led and implemented by Korea Hydro and Nuclear Power Co. (KHNP) which is the sole state-owned nuclear power project company spun off from Korea Electric Power Corporation (KEPCO) in 2001 as part of the government's program for electric industry restructuring. The cooperation between Romania and Korea in the nuclear power field began in March 2001. At industrial level a technical agreement between the Romanian Company Nuclearelectrica S.A. (SNN) and KHNP was signed in July 2003 for cooperation in Cernavoda NPP projects. The joint development of the Cernavoda NPP unit 3 was one of the major topics. Heavy water produced by Romanian Heavy Water plant at Drobeta Turnu Severin was supplied to KHNP (16 tones in 2001 and another 16 tones in 2004). The feasibility study for units 3 and 4 is being performed in two phases under leadership of SNN in cooperation with KHNP, AECL, ANSALDO and Deloitte and Touche as a financial advisor in Phase 2. It is expected that the appropriate securities

Management plan for the Nuclear Standards Program

International Nuclear Information System (INIS)

1979-11-01

This Management Plan was prepared to describe the manner in which Oak Ridge National Laboratory will provide technical management of the Nuclear Standards Program. The organizational structure that has been established within ORNL for this function is the Nuclear Standards Management Center, which includes the Nuclear Standards Office (NSO) already in existence at ORNL. This plan is intended to support the policies and practices for the development and application of technical standards in ETN projects, programs, and technology developments as set forth in a standards policy memorandum from the DOE Program Director for Nuclear Energy

Construction Improvement for the Korean Nuclear Program

International Nuclear Information System (INIS)

Yang, T. E.

1992-01-01

Construction of the nine Nuclear plants requires an enormous financial investment. The decision to build a nuclear unit is based on both economic and resource requirements. Korea has few natural resources to use for power generation so the use of diversified fuel sources is a part of the planning process. Nuclear has historically had economic advantages over the fossil fueled plant, however, this advantage has been reduced. This is mainly due to increasing decommissioning and waste disposal costs plus the financial outlays associated with gaining public acceptance of new nuclear units. One of the principal means to recover the economic advantage of a nuclear plant is to shorten the time needed for construction. Every extra day of construction costs large sums of money in interest and escalation expenses alone. The challenge is to shorten the construction period to the minimum feasible time and thereby reduce the financing costs. The methods that have to be employed to achieve this goal require the total commitment from the management of all entities involved in the program. Through the application of advanced management and construction techniques a new era in the construction of nuclear plants in Korea will occur. This will include changes to the methods used for managing, planning, licensing, designing and constructing the new plants. The ability to meet the aggressive plan for the construction of new nuclear power plants in Korea rests in the hands of the managers of all the parties involved. These men set all the rules by which the new plants will be constructed. It is their responsibility to tackle the current problems and develop the solutions to enable the plan to be realized. The changes suggested within this paper are major, but the potential benefits will allow the Korean Nuclear Industry to advance into the twenty first Century as a leader. The number of fully trained specialists needed to make this happen will not appear overnight. They will have to be

The north-Korean nuclear program. Round table. What do we know? What do we think we know? And what are the resulting actions?

International Nuclear Information System (INIS)

Pollack, J.

2004-06-01

The North-Korean nuclear program is problematic because of the specific government policy from which information are coming with difficulty. From open sources, the author takes stock on our knowledge concerning the military nuclear program of Pyongyang by looking on the two possible channels of nuclear matter production for nuclear weapons and on the weapons construction. He concludes on the actions to realize facing the uncertainties. (A.L.B.)

The international dimensions of nuclear safety standards

International Nuclear Information System (INIS)

Reed, J.M.

1992-01-01

The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

Anti-nuclear movement and art

International Nuclear Information System (INIS)

Go, Seung Woo; Yun, Beom Mo

1989-08-01

This book goes into in detail of nuclear weapon and independent unification in the Korean peninsula. So it describes how to build of peace of circumstances both inside and outside the Korean peninsula, how to deal with nuclear crisis of the Korean peninsula and to overcome nuclear crisis. Especially, this book deals with art which is used to resist nuclear and war including art activity for unity, anti-nuclear war, Kollwitz's etching as a connecting tool with public and a painting about atom bomb pictured by Maruky in Japan who worked for anti-nuclear war.

Performance Analysis of Korean Liquid metal type TBM based on Monte Carlo code

Energy Technology Data Exchange (ETDEWEB)

Kim, C. H.; Han, B. S.; Park, H. J.; Park, D. K. [Seoul National Univ., Seoul (Korea, Republic of)

2007-01-15

The objective of this project is to analyze a nuclear performance of the Korean HCML(Helium Cooled Molten Lithium) TBM(Test Blanket Module) which will be installed in ITER(International Thermonuclear Experimental Reactor). This project is intended to analyze a neutronic design and nuclear performances of the Korean HCML ITER TBM through the transport calculation of MCCARD. In detail, we will conduct numerical experiments for analyzing the neutronic design of the Korean HCML TBM and the DEMO fusion blanket, and improving the nuclear performances. The results of the numerical experiments performed in this project will be utilized further for a design optimization of the Korean HCML TBM. In this project, Monte Carlo transport calculations for evaluating TBR (Tritium Breeding Ratio) and EMF (Energy Multiplication factor) were conducted to analyze a nuclear performance of the Korean HCML TBM. The activation characteristics and shielding performances for the Korean HCML TBM were analyzed using ORIGEN and MCCARD. We proposed the neutronic methodologies for analyzing the nuclear characteristics of the fusion blanket, which was applied to the blanket analysis of a DEMO fusion reactor. In the results, the TBR of the Korean HCML ITER TBM is 0.1352 and the EMF is 1.362. Taking into account a limitation for the Li amount in ITER TBM, it is expected that tritium self-sufficiency condition can be satisfied through a change of the Li quantity and enrichment. In the results of activation and shielding analysis, the activity drops to 1.5% of the initial value and the decay heat drops to 0.02% of the initial amount after 10 years from plasma shutdown.

Materials Integrity Analysis for Application of Hyper Duplex Stainless Steels to Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Chang, Hyun Young; Park, Heung Bae; Park, Yong Soo; Kim, Soon Tae; Kim, Young Sik; Kim, Kwang Tae; Jhang, Yoon Young

2010-01-01

Hyper duplex stainless steels have been developed in Korea for the purpose of application to the seawater system of Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulating water pump headers, and the heat exchanged sea water is extracted to the discharge pipes in circulating water system connected to the circulating water discharge lines. The high flow velocity of some part of seawater system in nuclear power plants accelerates damages of components. Therefore, high strength and high corrosion resistant steels need to be applied for this environment. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of newly developed materials are quantitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld and HAZ (heat affected zone) are analyzed and the best compositions are suggested. The optimum conditions in welding process are derived for ensuring the volume fraction of ferrite(α) and austenite(γ) in HAZ and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured. As a result of all experiments, it was found that the newly developed hyper duplex stainless steel WREMBA has higher corrosion resistance and mechanical properties than those of super austenitic stainless steels including welded area. It is expected to be a promising material for seawater systems of Korean nuclear power plants

Nuclear radiation moisture gauge calibration standard

International Nuclear Information System (INIS)

1977-01-01

A hydrophobic standard for calibrating nuclear radiation moisture gauges is described. Each standard has physical characteristics and dimensions effective for representing to a nuclear gauge undergoing calibration, an infinite mass of homogeneous hydrogen content. Calibration standards are discussed which are suitable for use with surface gauges and with depth gauges. (C.F.)

Nuclear Control in Korean Peninsula: Status and Prospect

International Nuclear Information System (INIS)

Choe, Kwan-Kyoo

2007-01-01

This paper is aiming at finding out an authentic meaning of implementation of the IAEA Strengthened Safeguards System (SSS) in South Korea, and also the implementation of the joint agreement in North Korea concluded among the six nations on Feb. 13, 2007. The approach for development of the paper would be limited to the dimension of nuclear control. The actual implementation of the Additional Protocol (AP) and the entry into force of the Integrated Safeguards System in a near future in South Korea have passed a few of technical and diplomatic complications. Specially the past mistakes related to declaration to IAEA made by researchers resulted in a more strengthened transparency policy in South Korea, which was announced as a form of four-point statement reassuring the international community of its commitment to a nuclear-free policy on the Korean peninsula in 2004. North Korea rejected special inspection demanded by IAEA in 1992 related to its initial declaration to apply the IAEA INFCIRC/153 type of safeguards system. The rejection had consisted of the base line of diplomatic conflict between North Korea and international community. However, change of position of North Korea, even being uncertain still as of today, arrived at the joint declaration of '9-19' among 6 nations of Six-Party Talks in 2005, which developed into the conclusion of joint agreement for the implementation of the '9-19' principles on Feb. 13, 2007

Accelerating nuclear power standards development and promoting sound nuclear power development in China

International Nuclear Information System (INIS)

Yang Changli

2008-01-01

The paper expounds the importance of quickening establishment and perfection of nuclear power standard system in China, analyzes achievements made and problems existed during the development of nuclear power standards, put forward proposals to actively promote the work in this regard, and indicates that CNNC will further strengthen the standardization work, enhance coordination with those trades related to nuclear power standards, and jointly promote the development of nuclear power standards. (authors)

Technical standards in nuclear area

International Nuclear Information System (INIS)

Grimberg, M.

1978-01-01

The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

Aging management strategy for reactor internals of Korean nuclear power plants

International Nuclear Information System (INIS)

Hwang, Seong Sik; Kim, Soung Woo; Lee, Sam Lai; Hong, Seung Mo; Kim, Hong Pyo; Kim, Dong Jin; Lim, Yun Soo; Kim, Joung Soo; Jung, Man Kyo; Park, Jang Yul

2010-01-01

This report describes various factors on the IASCC of reactor internals in terms of fluence, stress, water chemistries and materials. Materials of each components of Korean nuclear power plants have been surveyed. A technical report for a management of reactor internals issued by EPRI was reviewed for a selection of most susceptible area among many components. Baffle former bolts are considered to be the most susceptible parts due to high irradiation level(fluence) and high tensile stress. Neutron fluence of Kori-1 and Kori-2 was calculated based on fuel exchange history, fuel performance and plant operation history. This report will be used for more advanced inspection and maintenance guidelines development by supplying inspection intervals and components (most susceptible regions) for the long term operation plants

Materials integrity analysis for application of POSCO developed STS to Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Hyun-Young, Ch.; Tae-Eun, J.; Young-Sik, K.

2009-01-01

Full text of publication follows: POSCO has developed duplex stainless steel (S32750) and hyper super duplex stainless steels for the purpose of using them in the secondary circulation cooling water system in Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulation pump headers and the heat exchanged sea water is extracted to the discharge pipes in circulation cooling water system connected to the circulation water discharge lines. The flow velocity of circulation cooling water system in nuclear power plants is high and damages of components from corrosion are severe. Therefore, this environment makes requiring of using high strength and high corrosion resistant steels. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of currently producing stainless steels and newly developed materials are qualitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld are analyzed and the best compositions of welding rod are suggested. The optimum weld condition is derived for ensuring HAZ phase ratios and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured using mock-up tube testers that are newly designed for this study. Coupons of candidate materials are introduced in the real system and corrosion resistance of them are analyzed. As results of all experiments, the current CCT and CPT criteria in Korean nuclear power plants are reviewed, and the more actual and strengthened criteria will be suggested. The real scale components made of newly developed hyper super duplex stainless steel will be applied to

Nuclear Data Verification and Standardization

Energy Technology Data Exchange (ETDEWEB)

Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

2011-10-01

The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

Korean Unification: Opportunities and Threats

National Research Council Canada - National Science Library

Bundy, Richard B

1992-01-01

.... in addition, they agreed to support the Korean peninsula as a nuclear free zone. The two countries have existed in fact since the partition of the peninsula after the allied victory over Japan In 1945...

Dynamic analysis of Korean nuclear fuel cycle with fast reactor systems

International Nuclear Information System (INIS)

Jeong, Chang Joon

2004-12-01

The Korean nuclear fuel cycle scenario was analyzed by the dynamic analysis method, including Pressurized Water Reactor (PWR), Canadian Deuterium Uranium (CANDU) and fast reactor systems. For the once-through fuel cycle model, the existing nuclear power plant construction plan was considered up to 2016, while the nuclear demand growth rate from the year 2016 was assumed to be 1%. After setting up the once-through fuel cycle model, the Korea Advanced Liquid Metal Reactor (KALIMER) scenario was modeled to investigate the fuel cycle parameters. For the analysis of the fast reactor fuel cycle, both KAILMER-150 and KALIMER-600 reactors were considered. In this analysis, the spent fuel inventory as well as the amount of plutonium, Minor Actinides (MA) and Fission Products (FP) of the recycling fuel cycle was estimated and compared to that of the once-through fuel cycle. Results of the once-through fuel cycle calculation showed that the demand grows up to 64 GWe and total amount of spent fuel would be ∼102 kt in 2100. If the KALIMER scenario is implemented, the total spent fuel inventory can be reduced by ∼80%. However it was found that the KALIMER scenario does not contribute to reduce the amount of MA and FP, which is important when designing a repository. For the further destruction of MA, an actinide burner can be considered in the future nuclear fuel cycle

Analysis of Koreans' Consciousness of 2016 by Using Wordcloud

International Nuclear Information System (INIS)

Roh, Seungkook; Jeong, Ik; Kim, Hyunjin; Sim, Kibo; Kim, Dongwook

2017-01-01

It is necessary for the Korean government and the atomic energy industry to grasp the current image of the Korean people on nuclear energy and to consider policy measures for enhancing the acceptance of nuclear energy over other agenda. In order to improve image of the nuclear energy and the contents analyzed in the previous section, we provide the following suggestions on the policy formulation of the government and the nuclear energy industry. The first is the expansion of related technology research to expand the safety of non-power generation and radioactive waste management in nuclear power generation. The second is building a new PR strategy for the nuclear power generation process and operation. This means that the nuclear industry needs to focus more on detailed information from the basic theory of nuclear power generation to the whole development process. It is necessary to establish a marketing strategy so that the site can be easily retrieved from internet portals such as Naver, Daum, and Google, portals most widely used by Internet users. Disaster response to nuclear power plant accident should be taught to the public by the government and the industry. After the screening of the Pandora movie, the Korean people became more interested in how to cope with serious accidents at nuclear power plants. Therefore, the government and the nuclear industry need to be more active in spreading to the public on the existing public evacuation tips.

Developing a Korean standard brain atlas on the basis of statistical and probabilistic approach and visualization tool for functional image analysis

Energy Technology Data Exchange (ETDEWEB)

Koo, B. B.; Lee, J. M.; Kim, J. S.; Kim, I. Y.; Kim, S. I. [Hanyang University, Seoul (Korea, Republic of); Lee, J. S.; Lee, D. S.; Kwon, J. S. [Seoul National University College of Medicine, Seoul (Korea, Republic of); Kim, J. J. [Yonsei University College of Medicine, Seoul (Korea, Republic of)

2003-06-01

The probabilistic anatomical maps are used to localize the functional neuro-images and morphological variability. The quantitative indicator is very important to inquire the anatomical position of an activated region because functional image data has the low-resolution nature and no inherent anatomical information. Although previously developed MNI probabilistic anatomical map was enough to localize the data, it was not suitable for the Korean brains because of the morphological difference between Occidental and Oriental. In this study, we develop a probabilistic anatomical map for Korean normal brain. Normal 75 brains of T1-weighted spoiled gradient echo magnetic resonance images were acquired on a 1.5-T GESIGNA scanner. Then, a standard brain is selected in the group through a clinician searches a brain of the average property in the Talairach coordinate system. With the standard brain, an anatomist delineates 89 regions of interest (ROI) parcellating cortical and subcortical areas. The parcellated ROIs of the standard are warped and overlapped into each brain by maximizing intensity similarity. And every brain is automatically labeled with the registered ROIs. Each of the same-labeled region is linearly normalize to the standard brain, and the occurrence of each region is counted. Finally, 89 probabilistic ROI volumes are generated. This paper presents a probabilistic anatomical map for localizing the functional and structural analysis of Korean normal brain. In the future, we'll develop the group specific probabilistic anatomical maps of OCD and schizophrenia disease.

Developing a Korean standard brain atlas on the basis of statistical and probabilistic approach and visualization tool for functional image analysis

International Nuclear Information System (INIS)

Koo, B. B.; Lee, J. M.; Kim, J. S.; Kim, I. Y.; Kim, S. I.; Lee, J. S.; Lee, D. S.; Kwon, J. S.; Kim, J. J.

2003-01-01

The probabilistic anatomical maps are used to localize the functional neuro-images and morphological variability. The quantitative indicator is very important to inquire the anatomical position of an activated region because functional image data has the low-resolution nature and no inherent anatomical information. Although previously developed MNI probabilistic anatomical map was enough to localize the data, it was not suitable for the Korean brains because of the morphological difference between Occidental and Oriental. In this study, we develop a probabilistic anatomical map for Korean normal brain. Normal 75 brains of T1-weighted spoiled gradient echo magnetic resonance images were acquired on a 1.5-T GESIGNA scanner. Then, a standard brain is selected in the group through a clinician searches a brain of the average property in the Talairach coordinate system. With the standard brain, an anatomist delineates 89 regions of interest (ROI) parcellating cortical and subcortical areas. The parcellated ROIs of the standard are warped and overlapped into each brain by maximizing intensity similarity. And every brain is automatically labeled with the registered ROIs. Each of the same-labeled region is linearly normalize to the standard brain, and the occurrence of each region is counted. Finally, 89 probabilistic ROI volumes are generated. This paper presents a probabilistic anatomical map for localizing the functional and structural analysis of Korean normal brain. In the future, we'll develop the group specific probabilistic anatomical maps of OCD and schizophrenia disease

Development of an accident consequence assessment code for evaluating site suitability of light- and heavy-water reactors based on the Korean Technical standards

Energy Technology Data Exchange (ETDEWEB)

Hwang, Won Tae; Jeong, Hae Sung; Jeong, Hyo Joon; Kil, A Reum; Kim, Eun Han; Han, Moon Hee [Nuclear Environment Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

Methodologies for a series of radiological consequence assessments show a distinctive difference according to the design principles of the original nuclear suppliers and their technical standards to be imposed. This is due to the uncertainties of the accidental source term, radionuclide behavior in the environment, and subsequent radiological dose. Both types of PWR and PHWR are operated in Korea. However, technical standards for evaluating atmospheric dispersion have been enacted based on the U.S. NRC's positions regardless of the reactor types. For this reason, it might cause a controversy between the licensor and licensee of a nuclear power plant. It was modelled under the framework of the NRC Regulatory Guide 1.145 for light-water reactors, reflecting the features of heavy-water reactors as specified in the Canadian National Standard and the modelling features in MACCS2, such as atmospheric diffusion coefficient, ground deposition, surface roughness, radioactive plume depletion, and exposure from ground deposition. An integrated accident consequence assessment code, ACCESS (Accident Consequence Assessment Code for Evaluating Site Suitability), was developed by taking into account the unique regulatory positions for reactor types under the framework of the current Korean technical standards. Field tracer experiments and hand calculations have been carried out for validation and verification of the models. The modelling approaches of ACCESS and its features are introduced, and its applicative results for a hypothetical accidental scenario are comprehensively discussed. In an applicative study, the predicted results by the light-water reactor assessment model were higher than those by other models in terms of total doses.

A study on the denuclearization policy in Korean peninsular

International Nuclear Information System (INIS)

Song, I. J.; Park, D. K.; Choi, Y. S.

2001-01-01

The prime ministers of North Korea and South Korea adopted 'Joint Declaration of the Denuclearization of the Korean Peninsular' (Joint Declaration) on December 31, 1991. Unprecedented as an agreement between two political powers of a divided country, this Joint Declaration is important for its historical significance. To analyze the denuclearization policy in the Korean peninsular, this dissertation suggests a framework which can be established on the factors facilitating the denuclearization both on the level of international politics and on the politics of a divided country. A substantial nuclear proliferation theory should be based on the study in detail of the nuclear proliferation cases of about 40 individual countries. This dissertation may be meaningful as a concrete study of the denuclearzation in the Korean peninsular on theoretical and practical basis

A seismic analysis of Korean standard PWR fuels under transition core conditions

International Nuclear Information System (INIS)

Kim, Hyeong Koo; Park, Nam Kyu; Jang, Young Ki; Kim, Jae Ik; Kim, Kyu Tae

2005-01-01

The PLUS7 fuel is developed to achieve higher thermal performance, burnup and more safety margin than the conventional fuel used in the Korean Standard Nuclear Plants (KSNPs) and to sustain structural integrity under increased seismic requirement in Korea. In this study, a series of seismic analysis have been performed in order to evaluate the structural integrity of fuel assemblies associated with seismic loads in the KSNPs under transition core conditions replacing the Guardian fuel, which is a resident fuel in the KSNP reactors, with the PLUS7 fuel. For the analysis, transition core seismic models have been developed, based on the possible fuel loading patterns. And the maximum impact forces on the spacer grid and various stresses acting on the fuel components have been evaluated and compared with the through-grid strength of spacer grids and the stress criteria specified in the ASME code for each fuel component, respectively. Then three noticeable parameters regarding as important parameters governing fuel assembly dynamic behavior are evaluated to clarify their effects on the fuel impact and stress response. As a result of the study, it has been confirmed that both the PLUS7 and the Guardian fuel sustain their structural integrity under the transition core condition. And when the damping ratio is constant, increasing the natural frequency of fuel assembly results in a decrease in impact force. The fuel assembly flexural stiffness has an effect increasing the stress of fuel assembly, but not the impact force. And the spacer grid stiffness is directly related with the impact force response. (author)

Cross-Cultural Aspect of Behavior Assessment System for Children-2, Parent Rating Scale-Child: Standardization in Korean Children

Science.gov (United States)

Song, Jungeun; Leventhal, Bennett L.; Koh, Yun-Joo; Cheon, Keun-Ah; Hong, Hyun Ju; Kim, Young-Key; Cho, Kyungjin; Lim, Eun-Chung; Park, Jee In

2017-01-01

Purpose Our study aimed to examine psychometric properties and cross-cultural utility of the Behavior Assessment System for Children-2, Parent Rating Scale-Child (BASC-2 PRS-C) in Korean children. Materials and Methods Two study populations were recruited: a general population sample (n=2115) of 1st to 6th graders from 16 elementary schools and a clinical population (n=219) of 6–12 years old from 5 child psychiatric clinics and an epidemiological sample of autism spectrum disorder. We assessed the validity and reliability of the Korean version of BASC-2 PRS-C (K-BASC-2 PRS-C) and compared subscales with those used for US populations. Results Our results indicate that the K-BASC-2 PRS-C is a valuable instrument with reliability and validity for measuring developmental psychopathology that is comparable to those in Western population. However, there were some differences noted in the mean scores of BASC-2 PRS-C between Korean and US populations. Conclusion K-BASC-2 PRS-C is an effective and useful instrument with psychometric properties that permits measurement of general developmental psychopathology. Observed Korean-US differences in patterns of parental reports of children's behaviors indicate the importance of the validation, standardization and cultural adaptation for tools assessing psychopathology especially when used in populations different from those for which the instrument was originally created. PMID:28120577

Cross-Cultural Aspect of Behavior Assessment System for Children-2, Parent Rating Scale-Child: Standardization in Korean Children.

Science.gov (United States)

Song, Jungeun; Leventhal, Bennett L; Koh, Yun Joo; Cheon, Keun Ah; Hong, Hyun Ju; Kim, Young Key; Cho, Kyungjin; Lim, Eun Chung; Park, Jee In; Kim, Young Shin

2017-03-01

Our study aimed to examine psychometric properties and cross-cultural utility of the Behavior Assessment System for Children-2, Parent Rating Scale-Child (BASC-2 PRS-C) in Korean children. Two study populations were recruited: a general population sample (n=2115) of 1st to 6th graders from 16 elementary schools and a clinical population (n=219) of 6-12 years old from 5 child psychiatric clinics and an epidemiological sample of autism spectrum disorder. We assessed the validity and reliability of the Korean version of BASC-2 PRS-C (K-BASC-2 PRS-C) and compared subscales with those used for US populations. Our results indicate that the K-BASC-2 PRS-C is a valuable instrument with reliability and validity for measuring developmental psychopathology that is comparable to those in Western population. However, there were some differences noted in the mean scores of BASC-2 PRS-C between Korean and US populations. K-BASC-2 PRS-C is an effective and useful instrument with psychometric properties that permits measurement of general developmental psychopathology. Observed Korean-US differences in patterns of parental reports of children's behaviors indicate the importance of the validation, standardization and cultural adaptation for tools assessing psychopathology especially when used in populations different from those for which the instrument was originally created.

Nuclear standards

International Nuclear Information System (INIS)

Fichtner, N.; Becker, K.; Bashir, M.

1981-01-01

This compilation of all nuclear standards available to the authors by mid 1980 represents the third, carefully revised edition of a catalogue which was first published in 1975 as EUR 5362. In this third edition several changes have been made. The title has been condensed. The information has again been carefully up-dated, covering all changes regarding status, withdrawal of old standards, new projects, amendments, revisions, splitting of standards into several parts, combination of several standards into one, etc., as available to the authors by mid 1980. The speed with which information travels varies and requires in many cases rather tedious and cumbersome inquiries. Also, the classification scheme has been revised with the goal of better adjustment to changing situations and priorities. Whenever it turned out to be difficult to attribute a standard to a single subject category, multiple listings in all relevant categories have been made. As in previous editions, within the subcategories the standards are arranged by organization (in Categorie 2.1 by country) alphabetically and in ascending numerical order. It covers all relevant areas of power reactors, the fuel cycle, radiation protection, etc., from the basic laws and governmental regulations, regulatory guides, etc., all the way to voluntary industrial standards and codes of pratice. (orig./HP)

Study on the Correlation between PSR and Korean Stress Test for Continued Operation of Aging NPP

International Nuclear Information System (INIS)

Chung, June Ho; Kim, Tae Ryong

2013-01-01

Nuclear Safety and Security Commission (NSSC), Korean nuclear regulatory authority established the stress test guideline based on the EU stress test, and KHNP prepared the execution plan in response to the guideline for the CO of Kori Unit 1 and Wolsong Unit 1. PSR is a comprehensive safety review program for long term operation of NPP, which was developed by IAEA. Korea adopted PSR in 1999 as the regulatory requirement for CO of NPP. The IAEA standard guideline for PSR program was updated in 2003. However, the Korean PSR has not been revised yet to apply the new IAEA guidelines. Additionally, national legal systems and guidelines associated with the adoption of stress tests are urgently required as well. These revisions are imperative in order to ensure the reliability of NPPs, and to promote public acceptance and understanding. This study presents the technical basis and proposals for review actions necessary to address the issues and controversies surrounding the continued operation and decommissioning of aging NPPs in Korea. As discussed earlier in characteristics of Korean Stress Test, it is more comprehensive than the EU Stress Test in terms of its multilateral evaluation which includes equipment durability, plant operation, human factors, and safety margins, hence substantially raising the significance and value of the evaluation process. Thus, the addition of Korean Stress Test to the existing Korean Evaluation of CO is expected to greatly increase the quality of safety assessment of aging NPPs in Korea due to its stricter safety policies, hence providing a more meaningful evaluation process. However, a one-time application of the Korean Stress Test to only Kori Unit 1 and Wolsong Unit 1 would be a waste of the great effort that has been done thus far to improve the Korean Evaluation of CO and develop the Korean Stress Test. By extending the Korean Stress Test to all NPPs in Korea would maintain and ensure the reliability of NPPs as well as public

Challenges of nuclear power for the sustainable role in Korean energy policy

International Nuclear Information System (INIS)

Lee, Y. E.

2007-01-01

This study aims to introduce the current role of nuclear power of Korea as the economic and low carbon emitter in the long term expansion planning and to improve the public acceptance of nuclear as the environmentally friendliness energy source. Nuclear and coal have been selected as the major electricity sources due to the insufficient domestic energy resources, and will provide more than 60% of total electricity generation in Korea for quite some time. National energy policy addressing environmental friendliness, stable supply and least cost has made it difficult to decide which energy resource is the best for the long term energy planning. Climate change regime will diminish the coal power plants in generation amount, the public still keeps nuclear at a distance and insists to replace nuclear by renewable and renewable doesn't any guarantee of stable supply although its economics is fast being improved. Therefore, it is necessary to analyze the long-term power expansion planning in various points of view such as environmental friendliness, benefit of carbon reduction and system reliability as well as least cost operation. The objective and approach of this study are to analyze the proper role of nuclear power by comparing the different types of scenarios in terms of the system cost changes, CO 2 emission reduction and system reliability. The results from this analysis are useful for the Korean government in charge of long-term energy policy to go over what kinds of role can each electric resources play and what are the best way to solve the triangular dilemma as economics, environmental friendliness, stable supply of the electricity

Imaginary Savior: the image of the nuclear bomb in Korea, 1945-1960.

Science.gov (United States)

Kim, Dong-Won

2009-01-01

Two atomic bombs dropped on Hiroshima and Nagasaki in August 1945 brought the unexpected liberation of Korea from the 35-year Japanese occupation. Koreans therefore had a very favorable and positive image of the nuclear bomb and nuclear energy from the beginning. The image of the nuclear bomb as "savior" was strengthened during the Korean War when the United States openly mentioned the possible use of the nuclear bomb against North Korean and Chinese military. After the end of the Korean War in July 1953 South Koreans strongly supported the development of the nuclear bomb in order to deter another North Korean invasion. When the US government provided South Korea with a research nuclear reactor in the late 1950s, most South Koreans hailed it as the first step to developing their own nuclear bomb. This paper will analyze how and why the savior image of the nuclear bomb originated and spread in Korea during the 1950s.

The current status and future prospects of the Korean nuclear power industry

International Nuclear Information System (INIS)

Lee, J. J.

2006-01-01

Recently, countries all over the world are becoming aware of the values and importance of nuclear energy which can help respond to energy crises caused by a sharp rise in oil prices and protect the earth from global warming. Since 1978, when Kori Unit 1(587MW), opened the nuclear generation era as a semi-domestic energy resource in Korea which is absolutely in short supply of energy, nuclear power generation in Korea has developed continuously for the past 28 years. Four new units including the Yonggwang 5 and 6 and Ulchin 5 and 6 have been successfully completed, raising the total nuclear installed capacity to 17,716MW from 20 units. At present, the nuclear generation in Korea is stably supplying about 40% of total electric generation, which is the fundamental energy of the nation, supporting the dynamic economic growth of Korea. In particular, Korean nuclear industry has been achieving excellent performance in nuclear power plant operation. The average capacity factor in 2005 hit the record of 95.5%, surpassing the previous record of 94.2% in 2003 in two years. Kori Unit 4 and another four units were listed at the top five in the capacity factor rating list of 2005 released by Nucleonics Week. In 2005, the site for radioactive waste disposal, which had been a long-cherished hope and the largest pending issue of the nuclear industry, was successfully selected in Korea through resident ballot as the first case of a national policy project, and as such, a national agenda was solved after 19 long years. Such a method in site selection has a significant meaning and establishes an excellent precedence; a large national policy project was decided upon by the residents themselves. As one of the model countries of building and operating nuclear power plants and technological independence, Korea is willing to contribute to the common goals of the world nuclear circle which can be summarized into energy security and environment preservation, by sharing accumulated

History and Reality:the background and origin of the North Korean nuclear crisis%历史与现实：朝鲜核危机的背景和缘起

Institute of Scientific and Technical Information of China (English)

程晓勇

2013-01-01

After the cold war, the North Korea nuclear problem become the dominant problem between U.S. - North Korean relationship, and became the profoundest factor to the regional security in the Korean Peninsula and Northeast A-sia. North Korea nuclear crisis is caused by complex and profound historical and realistic background. After World War I-I, the Korean Peninsula was split into two parts, the North and the South. Korean War in the 1950s’ and “cold peace”between the South and the North in the past forty years are the main causes of nuclear crisis in North Korea. Superfi-cially, North Korean nuclear crisis is the result of “nuclear proliferation”. However, if we probe into this problem further, we may find that the core reason of the North Korean nuclear crisis is the Korea Peninsula security pattern changes in the relations between DPRK rigid contradictions after the cold war.%　　朝鲜核危机是冷战后主导美朝关系，并深刻影响朝鲜半岛安全和东北亚地区稳定局势的最大因素。朝鲜核危机有着复杂而深刻的历史与现实背景，朝鲜半岛在二战后的南北分裂，上世纪50年代的朝鲜战争以及战后南北双方持续四十几年的“冷和平”状态，是朝核危机的深层次背景因素。表面上看，朝鲜核危机是由于“核扩散”而引发的，但是，透过朝核危机的表象，朝鲜核危机爆发的根本原因是冷战后朝鲜半岛安全格局发生的变化与朝美关系僵化不变的矛盾对立，是“此变”与“彼不变”对立冲突的结果。

Rape Myth Acceptance among Korean College Students: The Roles of Gender, Attitudes toward Women, and Sexual Double Standard

Science.gov (United States)

Lee, Joohee; Kim, Jinseok; Lim, Hyunsung

2010-01-01

The purpose of the current study was to examine factors that influence rape myths among Korean college students. This study was particularly interested in the ways in which attitudes toward women and sexual double standard affect the relationship between gender and rape myths. Although the incidence of rape is a common concern in many current…

Flooding PSA by considering the operating experience data of Korean PWRs

International Nuclear Information System (INIS)

Choi, Sun Yeong; Yang, Joon Eon

2007-01-01

The existing flooding Probabilistic Safety Analysis (PSA) was updated to reflect the Korean plant specific operating experience data into the flooding frequency to improve the PSA quality. Both the Nuclear Power Experience (NPE) database and the Korea Nuclear PIPE Failure Database (NuPIPE) databases were used in this study, and from these databases, only the Pressurized Water Reactor (PWR) data were used for the flooding frequencies of the flooding areas in the primary auxiliary building. With these databases and a Bayesian method, the flooding frequencies for the flooding areas were estimated. Subsequently, the Core Damage Frequency (CDF) for the flooding PSA of the UlChiN (UCN) unit 3 and 4 plants based on the Korean Standard Nuclear power Plant (KSNP) internal full-power PSA model was recalculated. The evaluation results showed that sixteen flooding events are potentially significant according to the screening criterion, while there were two flooding events exceeding the screening criterion of the existing UCN 3 and 4 flooding PSA. The result was compared with two kinds of cases: 1) the flooding frequency and CDF from the method of the existing flooding PSA with the PWR and Boiled Water Reactor (BWR) data of the NPE database and the Maximum Likelihood Estimate (MLE) method and 2) the flooding frequency and CDF with the NPE database (PWR and BWR data), NuPIPE database, and a Bayesian method. From the comparison, a difference in CDF results was revealed more clearly between the CDF from this study and case 2) than between case 1) and case 2). That is, the number of flooding events exceeding the screen criterion further increased when only the PWR data were used for the primary auxiliary building than when the Korean specific data were used

Nuclear security standard: Argentina approach

International Nuclear Information System (INIS)

Bonet Duran, Stella M.; Rodriguez, Carlos E.; Menossi, Sergio A.; Serdeiro, Nelida H.

2007-01-01

Argentina has a comprehensive regulatory system designed to assure the security and safety of radioactive sources, which has been in place for more than fifty years. In 1989 the Radiation Protection and Nuclear Safety branch of the National Atomic Energy Commission created the 'Council of Physical Protection of Nuclear Materials and Installations' (CAPFMIN). This Council published in 1992 a Physical Protection Standard based on a deep and careful analysis of INFCIRC 225/Rev.2 including topics like 'sabotage scenario'. Since then, the world's scenario has changed, and some concepts like 'design basis threat', 'detection, delay and response', 'performance approach and prescriptive approach', have been applied to the design of physical protection systems in facilities other than nuclear installations. In Argentina, radioactive sources are widely used in medical and industrial applications with more than 1,600 facilities controlled by the Nuclear Regulatory Authority (in spanish ARN). During 2005, measures like 'access control', 'timely detection of intruder', 'background checks', and 'security plan', were required by ARN for implementation in facilities with radioactive sources. To 'close the cycle' the next step is to produce a regulatory standard based on the operational experience acquired during 2005. ARN has developed a set of criteria for including them in a new standard on security of radioactive materials. Besides, a specific Regulatory Guide is being prepared to help licensees of facilities in design a security system and to fulfill the 'Design of Security System Questionnaire'. The present paper describes the proposed Standard on Security of Radioactive Sources and the draft of the Nuclear Security Regulatory Guidance, based on our regulatory experience and the latest international recommendations. (author)

Russia and the Issues of the Korean Peninsula

Directory of Open Access Journals (Sweden)

George D. Toloraya

2014-01-01

Full Text Available The importance of Korean Peninsula in Russian foreign strategy is based on the need to preserve peace and stability in the Russia's Far East "soft underbelly" and to be a part of international efforts to solve the Korean problem, as well as to promote regional economic cooperation. In 1990-s Russia's position on the peninsula weakened, mainly because of the rupture of ties with North Korea, while relations with South Korea were reactive in nature. Rebalancing relations with the two Koreas in 2000-s increased Russia's involvement into Korean settlement, including the 6- party format. Russia/s relations with North Korea are now based on good neighborhood principle, however, they are far from idyllic as Russia disapproves of Pyongyang's behavior, especially its nuclear and missile activities. However to influence the situation more Russia should deepen its ties with the current Pyongyang leadership regardless of how irritating its behavior might be. Relations with the ROK are aimed at becoming strategic, but in reality are limited due to ROK's alliance with the USA. However South Korea has become the third most important economic partner in Asia. Russia is especially interested in three- party projects, such as Trans-Korean railroad (linked to Transsiberan transit way, gas pipeline and electricity grid. However implementation of these project is negatively influenced by the tensions in Korean peninsula. It can be solved only by multilateral efforts for comprehensive solution combining security guarantees for North Korea and its abandonment of nuclear option.

ISO standardization in nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Brabec, D [Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia); Cermak, O [Urad pro Normalizaci a Mereni, Prague (Czechoslovakia)

1984-10-01

The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

Selecting safety standards for nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

Design reliability assurance program for Korean next generation reactor

International Nuclear Information System (INIS)

Lee, Beom-Su; Han, Jin-Kyu; Na, Jang Hwan; Yoo, Kyung Yeong

1997-01-01

The Korean Next Generation Reactor (KNGR) project is to develop standardized nuclear power plant design for the construction of future nuclear power plants in Korea. The main purpose of the KNGR project is to develop the advanced nuclear power plants, which enhance safety and economics significantly through the incorporation of design concepts for severe accident prevention and mitigation, supplementary passive safety concept, simplification and application of modularization and so on. For those, Probabilistic Safety Assessment (PSA) and availability study will be performed at the early stage of the design, and the Design Reliability Assurance Program (D-RAP) is applied in the development of the KNGR to ensure that the safety and availability evaluated in the PSA and availability study at the early phase of the design is maintained through the detailed design, construction, procurement and operation of the plants. This paper presents the D-RAP concept that could be applied at the stage of the basic design of the nuclear power plants, based on the models for the reference plants and/or similar plants. 4 refs., 1 fig

Harmonized technical standards in the nuclear field

International Nuclear Information System (INIS)

Carbone, Ferdinando

1976-01-01

The need was felt of harmonizing and gradually standardizing technical norms, from the well-known Anglo-Saxon type codes of practice to the equally well-known recommendations of the International Commission on Radiological Protection (ICRP). The latter provide the basis for the Euratom Directives (basic standards), which, following their adoption, were embodied in the national laws of community Member countries. ISO (International Standardization Organization) is active in the nuclear technical regulations field, in particular through its Committee ISO/TC 85 ''Nuclear Energy'' at international level and, in Italy, through the National Italian Unification Agency (UNI) and its Nuclear Unification Commission (UNICEN). At its XI plenary meeting this body, on the proposal of the Secretary-General, set up a Study Group to promote revision of the regulation in force and coordination between legislation and development of UNICEN standards, considered as a set of integrative industrial technical standards. CISDEN, the Italian Nuclear Energy Forum (FIEN) and other interested organizations have been invited to collaborate in this work. (N.E.A.)

ISO: international standards development for nuclear technology

International Nuclear Information System (INIS)

Becker, K.

1981-01-01

The importance of internationally recognized standards for nuclear technology and safety is rapidly increasing for technical as well as economical and political reasons such as public acceptance and nuclear technology transfer to developing countries. The need for such standards is also evident because of the large number of nuclear installations sited close to international borders, and the export of nuclear installations from relatively few supplier countries to a large number of user countries. It is the purpose of this report to describe briefly the history, organizational structures and procedures, goals, accomplishments, problems, and future needs of the relevant activities of the International Organization for Standardization (ISO). ISO is composed of the partly governmental, partly non-governmental national standards bodies of 86 countries including China. The work of its Technical Committee (TC) 85 'Nuclear Energy' is mostly concerned with industrial applications, contractual aspects and international communication, for the benefit of both developed and developing countries. It works in close liaison with IAEA, which develops Codes and Guides addressed mainly to the regulatory aspects of nuclear power plants in developing countries. ISO/TC 85 has four sub-committees dealing with: (a) Terminology, Definitions, Units and Symbols (Secretariat USA, four working groups (WGs)); (b) Radiation Protection (Secretariat France, ten WGs); (c) Power Reactor Technology (Secretariat Sweden, nine WGs); (d) Nuclear Fuel Technology (Secretariat F.R. Germany, seven WGs). (author)

Nuclear Data Center International Standard Towards TSO Initiative

International Nuclear Information System (INIS)

Raja Murzaferi Raja Moktar; Mohd Fauzi Haris; Siti Nurbahyah Hamdan

2011-01-01

Nuclear Data Center is the main facility for Nuclear Malaysia Agency IT infrastructure comprising of main critical servers, research and operational data storage, HPC-clusters system and vital network core equipment. In recent years, international body such as TIA-Telecommunication Industry Association and Up time Institute have came out with proper international data center standards in order to ensure data center operation on achieving maximum operational up time and minimal downtime. The standard are currently being rated as tier level ranging from Data Center tier I up to tier IV, differentiate by facility standard and up time/ downtime percentage ratio. This paper will discuss Nuclear Data Center adopting international standards in supporting Nuclear Malaysia TSO initiative thus ensuring the critical core component of agency IT services availability and further more International standard recognitions. (author)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Republic of Korea

International Nuclear Information System (INIS)

2009-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection) (Protection of workers; Protection of the public); 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Minister of Education, Science and Technology, including the Nuclear Energy Bureau; Minister of Knowledge Economy); 2. Advisory bodies (Atomic Energy Commission; Atomic Energy Safety Commission); 3. Public and semi-public agencies (Korean Atomic Energy Research Institute - KAERI; Korean Institute for Nuclear Safety - KINS; Korean Electric Power Company - KEPCO; Korean Hydro and Nuclear Power - KHNP)

Dictionary of the terms on nuclear scientific technique of France and Korea

Energy Technology Data Exchange (ETDEWEB)

NONE

1984-09-15

This book is a dictionary of the terms on nuclear scientific technique, which defines 3,400 terms and phrases in detailed explanation and lists in order of French, Korean and English. The terms are in alphabetical order, which are collision, elastic collision, nuclear fusion, fusion energy, absorption analysis, absorption curve, neutron, nuclear, radiation, radioactivity, reactor, nuclear disintegration, and so on. This book has appendixes on a standard unit, radiation size and unit, and the table of elements.

Dictionary of the terms on nuclear scientific technique of France and Korea

International Nuclear Information System (INIS)

1984-09-01

This book is a dictionary of the terms on nuclear scientific technique, which defines 3,400 terms and phrases in detailed explanation and lists in order of French, Korean and English. The terms are in alphabetical order, which are collision, elastic collision, nuclear fusion, fusion energy, absorption analysis, absorption curve, neutron, nuclear, radiation, radioactivity, reactor, nuclear disintegration, and so on. This book has appendixes on a standard unit, radiation size and unit, and the table of elements.

Nuclear reactor development in Korea: It's history and status

International Nuclear Information System (INIS)

Cheong, J.; Kim, I.; Kim, D. S.

2007-01-01

Currently in Korea, 20 nuclear plants are in operation, generating some 18,000 MWe of electricity which is about 30% of the national electricity supply. Further 8 reactors, including innovative light water reactors developed with 30 years' experience in construction and operation with continuous technology development, are either under construction or being planned. Executing an energetic program of nuclear development, Korea is now the world's sixth-ranked nuclear nation. In this paper, at first, history of the nuclear reactor development in Korea will be discussed including technology self-reliance efforts of the nuclear industry, and future plan and prospects will also be presented. Secondly, the OPR1000 which is a Korean standard plant will be introduced in detail including its characteristics, design approach and features. Six OPR1000's are being operated with outstanding performance and 4 more units are under construction. The APR1400, an upgraded reactor of the OPR1000 in capacity and design, has been developed as a next generation reactor, and the contracts were signed for the first 2 units' construction in August 2006. Its development process and design features will be described. Finally, Korea's efforts for future nuclear power generation will be introduced. For future reliable energy supply, Korea has been actively participating in international cooperation such as Gen IV International Forum. In summary, this paper will introduce the history and status of the Korean nuclear reactor development with its past, present and future, which might be helpful to understand the Korean nuclear industry and find a way for international cooperation especially with European countries

Aesthetics of Korean foods: The symbol of Korean culture

Directory of Open Access Journals (Sweden)

Hae-Kyung Chung

2016-09-01

Full Text Available Advances in transportation and communication have broken down critical barriers within the global economy, pushing us towards a more unified world. In keeping with this trend, processes of communication, transportation, and production are becoming increasingly standardized, mechanized, and automated. Yet as this global era of uniformity progresses, people and individuals will inevitably encounter identity confusion. Numerous individuals, ethnicities, nationalities, and countries around the world are working to counteract such identity confusion. As globalization progresses, groups and nationalities that fail to preserve their identities will dwindle and become absorbed by stronger entities. Therefore, many societies are investing great efforts into rediscovering and revamping their indigenous traditions, cultures, and customs. When travelers visit another country, one of the simplest avenues for them to experience the local culture is food. Unlike other cultural elements, many of which have become diluted because of globalization, native cuisines are still perceived as retaining the traditions, uniqueness, and diversity of individual cultures. It is more important than ever for people and countries to expand and preserve their respective cultural currencies. In this respect, taking a cultural approach to Korean cuisine is a fascinating and meaningful endeavor. In light of the recent publication of a few articles dealing with the symbolic significance and meaning behind Korean cuisine, an effort to compile a list of the distinctive cultural properties of Korean food seems vital. Furthermore, presenting the aesthetics of Korean food through a method that integrates science and culture is a very significant task. The authors of this paper firmly believe in its potential to advance the globalization of Korean food.

Korean experience on the development and deployment of nuclear power plants

International Nuclear Information System (INIS)

2009-01-01

The primary objective of the Republic of Korea's energy policy has been to secure an economical and stable supply of energy by diversifying energy sources. At present, environment-friendly energy policies have gained ground due largely to a progress in climate change convention negotiations. The impact of the two oil crises in the 1970s on the Korean economy was severe. In response, the government tried to limit the annual increase in energy consumption to about 7∼8%. By the 1990s, however, consumption was growing at more than 10% annually. The total primary energy consumption increased from 12.0 million TOE in 1965 to 233.4 million TOE in 2006. Due to the scarcity of indigenous energy resources, the Republic of Korea is heavily dependent upon imported energy. The overseas energy dependence continuously rises from 47.5% in 1970 to 96.5% in 2006. As in many other countries that are not endowed with fossil fuel reserves, nuclear power is considered to be the most reliable energy source capable of meeting the soaring energy demand necessary for economic development (i.e. an economic growth rate of some 10% per year). The Republic of Korea has consequently chosen nuclear power as one of its major energy sources

Classification of Korean native pear based on a standard set of microsatellite loci

Science.gov (United States)

After analysis with 12 microsatellite loci previously selected for use by ECPGR, 34 Korean pear accessions were classified into 3 groups. Group I included 4 Korean pea pears and one accession of P. calleryana. Group II contained 12 cultivars including 7 accessions presumed to belong to P. pyrifolia....

A study on the impact of the new international rules of the game (UR, the agreement on government procurement) and on the countermeasures for the Korean nuclear industry

International Nuclear Information System (INIS)

Lee, Kwang Suk; Song, Kee Dong; Ham, Chul Hoon; Kim, Seung Soo; Koh, Han Suk

1994-08-01

The purpose of this study is to analyze the impact of such changes in the rules of the game on the Korean nuclear industry and to propose possible countermeasures in short-term and long-term perspectives at the national level. This study also has an educational purpose to help people. working in the nuclear field understand the significance of the changes in the rules of the game. This study looks through the history and contents of the GATT system, the UR, the AGP, and the post-UR movement, providing some insight on the current trend in the rules of the game. Also this study analyzes the impact of the changes in the rules of the game on the Korean nuclear industry in qualitative terms, and proposes possible short-term and long-term countermeasures at the national level in both perspectives of utility and nuclear industry. 5 figs, 15 tabs, 51 refs. (Author)

A study on the impact of the new international rules of the game (UR, the agreement on government procurement) and on the countermeasures for the Korean nuclear industry

Energy Technology Data Exchange (ETDEWEB)

Lee, Kwang Suk; Song, Kee Dong; Ham, Chul Hoon; Kim, Seung Soo; Koh, Han Suk [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-08-01

The purpose of this study is to analyze the impact of such changes in the rules of the game on the Korean nuclear industry and to propose possible countermeasures in short-term and long-term perspectives at the national level. This study also has an educational purpose to help people. working in the nuclear field understand the significance of the changes in the rules of the game. This study looks through the history and contents of the GATT system, the UR, the AGP, and the post-UR movement, providing some insight on the current trend in the rules of the game. Also this study analyzes the impact of the changes in the rules of the game on the Korean nuclear industry in qualitative terms, and proposes possible short-term and long-term countermeasures at the national level in both perspectives of utility and nuclear industry. 5 figs, 15 tabs, 51 refs. (Author).

Korean efforts for education and training network in nuclear technology

International Nuclear Information System (INIS)

Han, Kyong-Won; Lee, Eui-Jin

2007-01-01

Nuclear energy has been a backbone for Korea's remarkable economic growth, and will continue its essential role with 18 nuclear power plants in operation, 2 more units under construction, 6 more units in planning. Korea is operating its own designed nuclear power plants, such as KSNP, 1400, as well as self-design and operation of 30 MW Hanaro research reactor. Korea makes strong efforts to develop future nuclear technology. They are the System-Integrated Modular Advanced Reactor, SMART, Korea Advanced Liquid Metal reactor, KALIMER, Hydrogen Production reactor, and Proliferation-resistant Nuclear Fuel Cycle. In parallel, Korea is establishing an Advanced Radiation Technology R and D Center and a High Power Proton Accelerator Center. International, next generation nuclear power technologies are being developed through projects such as the IAEA Innovative Nuclear Reactors and Fuel Cycle, INPRO, Generation IV International Forum, GIF, and International thermonuclear Experimental reactor, ITER. In the new millennium, Korea expects that radiation technology combined with bio, nano, and space technology will sustain our civilization. About 21,000 qualified nuclear human resources are engaged in power and non-power fields such as design and manufacturing of equipment, plant operation and maintenance, safety, RI production, R and D, etc. However, it is recognized that the first generation of nuclear work force is getting older and retired, less of our youth are studying nuclear science and engineering. Korean Government has established a promotion program on nuclear human resources development, which is needed until 2010. For the sustainable development of nuclear science and technology, it calls for more qualified human resources. We ought to encourage our youth to become more interested in nuclear studies and careers. Korea is making strong efforts to support nuclear education and training for young generations. It is believed that internationally accepted advanced

Radiological and nuclear safety- evolution, standards and similarity

International Nuclear Information System (INIS)

Soman, S.D.

1996-01-01

With the realisation of potential for severe health affects after the discovery of x-rays and radioactivity, the radiation protection aspect became focus of interest for medical users from the beginning of this century. With the activities of International Commission on Radiological Protection (ICRP), the standards evolved during all these years based on epidemiological data and radio-biological research. The current standards are the ICRP recommendations of 1990. Based on these, internationally harmonised standards for protection against ionising radiation and safety of radioactive sources were brought out by IAEA in 1994. The nuclear safety (implies safety of nuclear power plants) came into prominence when large scale units were designed and operated since mid 1950s. The philosophy in nuclear safety has evolved in past 2-3 decades taking into account the lessons learned from accidents, mainly Three Mile Island (1979) and Chernobyl-4 (1986). These current nuclear safety standards are incorporated in INSAG reports, particularly INSAG-3. This paper brings out salient features of these evolutions, current standards and similarity of radiation and nuclear safety standards in their present form. (author). 7 refs., 10 tabs

ISO standardization in nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Brabec, D. (Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia)); Cermak, O. (Urad pro Normalizaci a Mereni, Prague (Czechoslovakia))

1984-10-01

The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

A perspective of the evolving nuclear power programs in the Asia-Pacific region

International Nuclear Information System (INIS)

Langmo, A.

1994-01-01

This paper reviews the issues related to the need for nuclear power in the Asia-Pacific region. It further discusses the benefits for nuclear power introduction, as they have been reported in countries with significant nuclear power programs and as they are now being computed and forecasted in this region. A large body of experience in commercializing and operating nuclear power plants bas been accumulated worldwide and some of the most significant nuclear power achievements have occurred in this region. Examples are the large nuclear plants standardisation program implemented in Japan, culminating in the construction of the two advanced boiling water reactors (ABWRs) in Kashiwakaki-Kariwa and the recent record short 48 months construction time for Hamaoka - 4 unit, the Korean standard nuclear plant design and the impressively high lifetime capacity factors achieved in the Korean and Taiwanese nuclear power programs. These and other examples enhance the confidence that further nuclear power expansion can be implemented successfully in the Asia-Pacific region, and provide the region with the benefits of large scale economic supply of electricity required for future economic development. 16 figs

Nuclear radiation gauge standard

International Nuclear Information System (INIS)

Berry, R.L.

1977-01-01

A hydrophobic standard for calibrating nuclear radiation moisture gauges is described, comprising a body of superposed interleaved thin layers of a moderating material containing hydrogen in the molecular structure thereof and of a substantially non-moderating material

ASME nuclear codes and standards risk management strategic plan

International Nuclear Information System (INIS)

Balkey, Kenneth R.

2003-01-01

Over the past 15 years, several risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to better manage the numerous initiatives in the future, the ASME Board on Nuclear Codes and Standards has recently developed and approved a Risk Management Strategic Plan. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent issuance of the ASME Standard for Probabilistic Risk Assessment (PRA) for Nuclear Power Plant Applications. The paper discusses potential applications within ASME Nuclear Codes and Standards that may require expansion of the PRA Standard, such as for new generation reactors, or the development of new PRA Standards. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, and related U.S. regulatory activities are also summarized. (author)

Future direction of ASME nuclear codes and standards

International Nuclear Information System (INIS)

Ennis, Kevin; Sheehan, Mark E.

2003-01-01

While the nuclear power industry in the US is in a period of stasis, there continues to be a great deal of activity in the ASME nuclear standards development arena. As plants age, the need for new approaches in standardization changes with the changing needs of the industry. New tools are becoming available in the form of risk analysis, and this is finding its way into more and more of ASME's standards activities. This paper will take a look at the direction that ASME nuclear Codes and Standards are heading in this and other areas, as well as taking a look at some advance reactor concepts and plans for standards to address new technologies

Proprietary, standard, and government-supported nuclear data bases

International Nuclear Information System (INIS)

Poncelet, C.G.; Ozer, O.; Harris, D.R.

1975-07-01

This study presents an assessment of the complex situation surrounding nuclear data bases for nuclear power technology. Requirements for nuclear data bases are identified as regards engineering functions and system applications for the many and various user groups that rely on nuclear data bases. Current practices in the development and generation of nuclear data sets are described, and the competitive aspect of design nuclear data set development is noted. The past and current role of the federal government in nuclear data base development is reviewed, and the relative merits of continued government involvement are explored. National policies of the United States and other industrial countries regarding the availability of nationally supported nuclear data information are reviewed. Current proprietary policies of reactor vendors regarding design library data sets are discussed along with the basis for such proprietary policies. The legal aspects of protective policies are explored as are their impacts on the nuclear power industry as a whole. The effect of the regulatory process on the availability and documentation of nuclear data bases is examined. Current nuclear data standard developments are reviewed, including a discussion of the standard preparation process. Standards currently proposed or in preparation that directly relate to nuclear data bases are discussed in some detail. (auth)

The status of AOA and the CRUD deposition in Korean PWR

International Nuclear Information System (INIS)

Maeng, Wan Young; Choi, Byung Seon; Min, Duck Kee; Kwon, Hyung Moon; Choi, In Kyu; Yeon, Je Won; Kim, Jae Ik; Woo, Hae Seuk; Kim, Young Koo; Park, Jong Youl

2009-01-01

Korean nuclear power plants have experienced several times of AOA (Axial Offset Anomaly). AOA in Korean plants seems to be the consequence of high burn-up and long term cycle of the nuclear fuel as experienced in the foreign plants. The root cause of AOA is not clearly understood until now. Even though plants which have similar operation condition (similar thermo-hydraulic condition, water chemistry and structural materials), the AOA behavior of each plant is different from other plants. To have an understanding of the plant specific behavior of each plant and to have the countermeasures to AOA, the mechanism of CRUD deposition should be clarified. The purpose of this study is to investigate the AOA status and the CRUD characteristics in Korean power utilities. We surveyed the current AOA occurrence history and collected the Korean CRUD data which are scattered in various sources. To have some understanding on the key variables of AOA, we built experimental apparatus for CRUD deposition in simulated PWR environment. The status and the investigation plans of our experimental study are introduced in the paper

Working out the standards for nuclear power aging management implementation (PLM Standards)

International Nuclear Information System (INIS)

Miyano, Hiroshi

2008-01-01

Background of preparation of standards, preparation of standards for development of nuclear power aging management technologies, revision of PLM (Product Lifecycle Management) standards, and problems of PLM standards are stated. The placement of social needs, scheme, the standards system, preparation of rules and standards, and practical use of them by road map are illustrated and explained. Relation between the safety regulations and examination standards, and development and preparation of standards system are outlined. The nuclear power plant aging management and the maintenance control are provided by many rules and standards. PLM standards defines the aging phenomena and extracts the measurements and reflects them on the usual maintenance flow under the long term maintenance program. New examination system constructs the usual maintenance and the maintenance based on the aging management and long term maintenance program. Outline and construction of PLM standards are explained with notes and additional books. (S.Y.)

Development of Safety Culture Assessment Strategy for Korean NPP

International Nuclear Information System (INIS)

Park, Jung Hwan; Kim, Jong Hyun

2014-01-01

This paper aims at developing the requirements for a method to evaluate the operational safety culture, evaluating currently available methods based on the requirements, and suggesting a method to evaluate and improve the operational safety culture for Korean nuclear power plants. This paper reviews the widely-used methods to assess safety culture for NPPs and their basis. Then, this paper develops the requirements for the method to evaluate operational safety culture for Korean NPPs. Based on these requirements, Korean Safety Culture Indicators (KSCI) and evaluation measures are also suggested. Finally this paper proposes the guidelines to develop improvements to safety culture from the evaluation results

Development of Safety Culture Assessment Strategy for Korean NPP

Energy Technology Data Exchange (ETDEWEB)

Park, Jung Hwan; Kim, Jong Hyun [KEPCO, Ulsan (Korea, Republic of)

2014-08-15

This paper aims at developing the requirements for a method to evaluate the operational safety culture, evaluating currently available methods based on the requirements, and suggesting a method to evaluate and improve the operational safety culture for Korean nuclear power plants. This paper reviews the widely-used methods to assess safety culture for NPPs and their basis. Then, this paper develops the requirements for the method to evaluate operational safety culture for Korean NPPs. Based on these requirements, Korean Safety Culture Indicators (KSCI) and evaluation measures are also suggested. Finally this paper proposes the guidelines to develop improvements to safety culture from the evaluation results.

Studies on the reference Korean and estimation of radiation exposure dose

International Nuclear Information System (INIS)

Kim, Y.J.; Lee, K.S.; Chun, K.J.; Kim, J.B.; Chung, G.H.; Kim, S.R.

1982-01-01

For the purpose of establishment of Reference Korean and estimation of internal and external exposure doses in the Reference Korean, we have surveyed reference values for Koreans such as physical standards including height, weight, and body surface area, food consumption rate of daily intake of radioactive substances and exposure dose from natural radiation. (Author)

A Study on distinguishing seismic waves caused by natural earthquakes and underground nuclear explosion within North Korean Context

Science.gov (United States)

Premlet, B.; Sabu, S.; Kamarudheen, R.; Subair, S.

2017-12-01

Since the first nuclear test on 15 July 1945 , there have been over 2,051 other weapon tests around the world . The waveforms of a natural earthquake which generates strong S waves and an underground explosion which is dominated by P waves were distinguished from the analysis of data corresponding to a 2005 M5.0 Earthquake and a 2016 North Korean nuclear test , both at similar distances from seismometer . Further differences between the seismograms were evaluated and successfully distinguished between the origins of the elastic waves through the data using Moment Tensor Solution using stations BJT , HIA and INCN . North Korea has developed a nuclear fuel cycle capability and has both plutonium and enriched uranium programs at Pyongyang . Seismic recordings of vertical ground motion at Global Seismographic Network station IC.MDJ of the 4 seismic events at Punggye-ri , North Korea , which occurred on the 9th of October 2006 , 25th of May 2009, 12th of February 2013 and on the 6th of January and 9th of September , 2016 were examined and the P waves of these seismic waves , which show very similar wave form , were inspected and compared to the seismic data of the latest underground nuclear test on the 3rd of September 2017 at 03:30 UTC at the same site which is many times more powerful than the previous tests . The country , which is the only nation to have tested nuclear weapons in this millennium , has successfully prevented the release of radioactive isotopes and hampered data collection but further studies were done using acoustic data which was analysed from sonograms of the 4 North Korean tests at station MDJ. The latest explosion data from 3rd September was also compared to 42 presumed underground explosions which occurred in China , India , the U.S.S.R , Iran , Turkey and recorded at Arkansas Seismic Network.

Reactor laboratory course for Korean under-graduate students in Kyoto University Critical Assembly (KUGSiKUCA)

International Nuclear Information System (INIS)

Pyeon, Cheol Ho; Misawa, Tsuyoshi; Unesaki, Hironobu; Ichihara, Chihiro; Shiroya, Seiji; Whang, Joo Ho; Kim, Myung Hyun

2005-01-01

The Reactor Laboratory Course for Korean Under-Graduate Students has been carried out at Kyoto University Critical Assembly of Japan. This course has been launched from fiscal year 2003 and has been founded by Ministry of Science and Technology of Korean Government. Since then, the total number of 43 Korean under-graduate students, who have majored in nuclear engineering of 6 universities in all over the Korea, has been taken part in this course. The reactor physics experiments have been performed in this course, such as Approach to criticality, Control rod calibration, Measurement of neutron flux and power calibration, and Educational reactor operation. As technical tour of Japan, nuclear site tour has been taken during their stay in Japan, such as PWR, FBR, nuclear fuel company and some institutes

A Study on the Korean Medicine Education and the Changes in the Traditional Korean Medicine during the Japanese Colonial Era: Focused on the Korean Medicine Training Schools.

Science.gov (United States)

Huang, Yongyuan

2018-04-01

standard education of Korean medicine but also aimed to lay their foundation in the education system of the Western medical science by forming the separated curriculum including basic medical science, diagnosis, clinic, drug, and the practice of acupuncture and moxibustion. Furthermore, having contained the basic subjects of the Western medical science - physiology, anatomy, pathology, etc. - in the compulsory subjects shows perceiving the intellectual and systematic hegemony of the Western medical science and satisfying the demand of the colonial power. Such an education system was succeeded and solidified through the training sessions and the training schools operated by the local colonial governments after the 1930s. Korean medicine became different from the traditional Korean medicine through the establishment and the operation of such training schools.

Safety standards and safety record of nuclear power plants

International Nuclear Information System (INIS)

Davis, A.B.

1984-01-01

This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

ASME nuclear codes and standards risk management strategic planning

International Nuclear Information System (INIS)

Hill, Ralph S. III; Balkey, Kenneth R.; Erler, Bryan A.; Wesley Rowley, C.

2007-01-01

This paper is prepared in honor and in memory of the late Professor Emeritus Yasuhide Asada to recognize his contributions to ASME Nuclear Codes and Standards initiatives, particularly those related to risk-informed technology and System Based Code developments. For nearly two decades, numerous risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to properly manage the numerous initiatives currently underway or planned for the future, the ASME Board on Nuclear Codes and Standards (BNCS) has an established Risk Management Strategic Plan (Plan) that is maintained and updated by the ASME BNCS Risk Management Task Group. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent probabilistic risk assessment (PRA) standards developments for nuclear power plant applications. The paper discusses planned applications within ASME Nuclear Codes and Standards that will require expansion of the ASME PRA Standard to support new advanced light water reactor and next generation reactor developments, such as for high temperature gas-cooled reactors. Emerging regulatory developments related to risk-informed, performance- based approaches are summarized. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is also summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, including related U.S. regulatory activities. (author)

Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

2000-12-15

The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

Brief overview of American Nuclear Society's research reactor standards

International Nuclear Information System (INIS)

Richards, Wade J.

1984-01-01

The American Nuclear Society (ANS) established the research reactor standards group in 1968. The standards group, known as ANS-15, was established for the purpose of developing, preparing, and maintaining standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training

Department of Energy Nuclear Energy Standards Program

International Nuclear Information System (INIS)

Silver, E.G.

1980-01-01

The policy with respect to the development and use of standards in the Department of Energy (DOE) programs concerned with maintaining and developing the nuclear option for the civilian sector (both in the form of the currently used light water reactors and for advanced concepts including the Liquid Metal Fast Breeder Reactor), is embodied in a Nuclear Standards Policy, issued in 1978, whose perspectives and philosophy are discussed

Personnel involved in nuclear standards development: 1980 directory

International Nuclear Information System (INIS)

Carr, S.J.

1980-03-01

The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development

Personnel involved in nuclear standards development: 1980 directory

Energy Technology Data Exchange (ETDEWEB)

Carr, S.J. (ed.)

1980-03-01

The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

Present problems of standardization in nuclear instrumentation in Romania

International Nuclear Information System (INIS)

Purghel, Lidia

2001-01-01

The continuos development of nuclear techniques, based on international cooperation, led to the need for producing national and international standards referring to terminology, classification, technical characteristic, testing and calibration methods for nuclear instrumentation. The international standardization activity is organised in the frame of the well-known organization like IEC, ISO, ICRU, ICRP, IOLM, CENELEC, EFOMP, WHO. High advances were obtained in the standardization of the ionising radiation dosimetry in the frame of the International Commission for Radiation Units (ICRU) which started its works 1925. Romania is member of the International Electrotechnical Commission (IEC) from 1920 when its president was the formal member of Romanian Academy, professor Remus Radulet. Romania is effectively involved in standardization activities in the field nuclear instrumentation both as user and manufacturer of nuclear instrumentation. At national level the Technical Committee 45, as a branch of the Romanian Electrotechnical Committee is hosted by Horia Hulubei National Institute for Physics and Nuclear Engineering. The technical committee has the tasks of analysing the market, the regulations and the industry requirements and proposing new standards or revision for existing one. A table is given showing the number of IEC standards considered by TC 45, adopted RS - IEC standards (prepared/published) and planned for 2000/2001. Romania hosted IEC international plenary meetings in 1962 and 1974 and an IEC workshop 1997 with participation of specialists from USA, Sweden, Germany, France, Japan and Romania. As industry is striving to use more and more standard products, that means best quality and safety for less money, more than ever one have to convince the industry about the usefulness and specificity of the nuclear standards

INDC/NEANDC nuclear standards file 1980 version

International Nuclear Information System (INIS)

1981-09-01

This working document of the Nuclear Standards Subcommittee of the International Nuclear Data Committee (INDC) summarizes the status of nuclear standards as of the 11th INDC meeting (6/'80) with selective updating to approximately 5/'81. This version of the file is presented in two sections as per the following. The first section (A) consists of numerical tabulations of the respective quantities generally including quantitative definition of the uncertainties. Most of these numerical values are taken from the ENDF/B-V file which is available on a world-wide basis through the 4-Center network. Some guidelines as to appropriate usage are also given. The objective is the provision of a concise and readily used reference guide to essential standard-nuclear quantities useful for a diversity of basic and applied endeavors. The second section (B) briefly summarizes the contemporary status of each of the standards tabulated in Section A and additional items, including recent relevant work and areas of continuing uncertainty. These brief reviews were prepared under the auspices of the Committee by outstanding specialists in the respective fields. In many instances they are new statements but, where review indicates that the previous statement (see INDC-30/L+sp) remains appropriate, the previous summaries were retained; often with additional remarks by the editor

Trends in U.S. nuclear standards development

International Nuclear Information System (INIS)

Crowley, J.H.; Kaminski, R.S.

1987-01-01

Regulation of the U.S Nuclear Power industry has been extensive during the 1970's. Key to this situation has been the evolution in the 'interpretation' of the rules, regulations and consensus standards which have been incorporated into NRC guidance documents by reference or endorsement. The resulting increase in the number and complexity of LWR construction requirements has significantly increased the labor content of an LWR construction project. The authors believe that existing nuclear related consensus standards should be reviewed with the objective of modifying the standards to improve the efficiency and productivity of engineering, craft, and non-manual personnel. (author)

International implications of nuclear Q.A. standards

International Nuclear Information System (INIS)

Stoddart, D.E.

1976-01-01

The work of the International Atomic Energy Agency (I.A.E.A.) in the field of Quality Assurance is aimed at preparing a Code of Practice covering recommendations on safety aspects only which is designed to be usable by all nations. This Code is followed up by a series of Safety Guides as aids to developing nations faced with the need to regulate and assure safety, reliability and quality. The I.A.E.A. Code is not written as a mandatory document and it can only recommend and therefore the term 'should' is used throughout. The International Organization for Standardization (I.S.O.) is concerned with producing standards and as such the proposed I.S.O. draft standard on 'Quality Assurance for Nuclear Power Plants' is written in mandatory language, it uses the word 'shall'. The I.S.O. standard will also cover not only safety aspects but also those of a successfully operating nuclear power plant. The I.S.O. Working Group is charged with producing standards on quality assurance covering the design, procurement, fabrication, construction, operation, maintenance and decommissioning of structure, systems and components of nuclear power plants. The work of both organizations is discussed briefly. (author)

Harmonization of nuclear codes and standards. Pacific nuclear council working and task group report

International Nuclear Information System (INIS)

Dua, Shami

2008-01-01

Nuclear codes and standards have been an integral part of the nuclear industry since its inception. As the industry came into the main stream over the 2nd half of the 20th century, a number of national and international standards were developed to support a specific nuclear reactor concept. These codes and standards have been a key component of the industry to maintain its focus on nuclear safety, reliability and quality. Both national and international standards have served the industry well in obtaining public, shareholder and regulatory acceptance. The existing suite of national and international standards is required to support the emerging nuclear renaissance. However as noted above under Pacific Nuclear Council (PNC), Manufacturing Design Evaluation Program (MDEP) and SMiRT discussions, the time has come now for the codes and standards writing bodies and the industry to take the next step to examine the relevance of existing suite in view of current needs and challenges. This review must account for the changing global environment including global supply chain and regulatory framework, resources, deregulation, free trade, and industry need for competitiveness and performance excellence. The Task Group (TG) has made limited progress in this review period as no additional information on the listing of codes and standards have been received from the members. However, TG Chair has been successful in obtaining considerable interest from some additional individuals from the member countries. It is important that PNC management seek additional participation from the member countries and asks for their active engagement in the Working Group (WG) TG activities to achieve its mandate and deliverables. The harmonization of codes and standards is a key area for the emerging nuclear renaissance and as noted by a number of international organizations (refer to MDEP action noted above) that these tasks can not be completed unless we have the right level of resources and

LDC nuclear power: Republic of South Korea

International Nuclear Information System (INIS)

Ha, Y.S.

1982-01-01

This chapter elaborates on the major factors contributing to the development of the South Korean nuclear energy program during the last three decades. The history of Korean nuclear development followed three phases: (1) early nuclear developments (1954-1961); (2) the beginning of a nuclear power program (1962-1971); and (3) the development of a nuclear power program (1972-1981). Factors which could interrupt nuclear development are the risk of proliferation, national security, and reversals in the nuclear programs of Japan, France, and West Germany. 66 references, 1 figure, 3 tables

Development of Korean EDMG

Energy Technology Data Exchange (ETDEWEB)

Kim, Yunjung; Jee, Moonhak; Kim, Inhwan; Park, Munhee [Nuclear Safety Technology Research Laboratory, Daejeon (Korea, Republic of); Kim, Moonoh [Atomic Creative Technology, Seoul (Korea, Republic of)

2014-05-15

Safety feature is also needed to more effectively cope with site-wide events affecting multiple units. In this study, the accident mitigation approaches in US are reviewed. The most effective ways to strengthen the defense-in-depth of nuclear power installations are presented as EDMG(Extensive Damage Mitigation Guideline) and FLEX against extreme hazards such as a beyond-design-basis external event (BDBEE) that took place at Fukushima. A combination of the US EDMG and FLEX is applied to develop Korean EDMG, which will be developed to have two different types of EDMGs : 'Site EDMG' to be used for effective technical support to activated TSCs and management of corporate emergency response resources in coordination with the EOF as necessary; and 'Plant-Specific EDMG (for Extreme Event)' to be used by the Technical Support Center (TSC) of a unit where a total loss of control has occurred or plant control cannot be established from the Control Room and Remote Shutdown Panel. The development of Korean EDMG is expected to further enhance mitigation and coping capabilities against site-wide extreme hazard in Korea where a relatively large number of units are assembled on each nuclear power plant site.

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Effects of Psychiatric Symptoms on Attention in North Korean Refugees.

Science.gov (United States)

Lee, Yu Jin; Jun, Jin Yong; Park, Juhyun; Kim, Soohyun; Gwak, Ah Reum; Lee, So Hee; Yoo, So Young; Kim, Seog Ju

2016-09-01

We investigated the performance of North Korean refugees on attention tasks, and the relationship between that performance and psychiatric symptoms. Sustained and divided attention was assessed using the computerized Comprehensive Attention Test in North Korean refugees and in South Koreans. All participants also completed the Beck Depression Inventory, the Beck Anxiety Inventory, the Impact of Event Scale-Revised and the Dissociative Experiences Scale-II (DES-II). The North Korean refugees showed slower reaction times (RTs) on the visual sustained attention task compared to the South Koreans after controlling for age and sex. North Korean refugees had a greater number of omission errors (OEs) on the divided attention task and a higher standard deviation (SD) of RT. Total DES-II scores of the North Korean refugees were associated with the number of OEs and the SD of RT on the sustained attention task, and with the number of OEs on the divided attention task. North Korean refugees showed poorer performance on computerized attention tasks. In addition, attention deficit among North Korean refugees was associated with their dissociative experiences. Our results suggest that refugees may have attention deficits, which may be related to their psychiatric symptoms, particularly dissociation.

The Korean nuclear power program

International Nuclear Information System (INIS)

Choi, Chang Tong

1996-01-01

Although the world nuclear power industry may appear to be in decline, continued nuclear power demand in Korea indicates future opportunities for growth and prosperity in this country. Korea has one of the world's most vigorous nuclear power programs. Korea has been an active promoter of nuclear power generation since 1978, when the country introduced nuclear power as a source of electricity. Korea now takes pride in the outstanding performance of its nuclear power plants, and has established a grand nuclear power scheme. This paper is aimed at introducing the nuclear power program of Korea, including technological development, international cooperation, and CANDU status in Korea. (author). 2 tabs

Management of immune thrombocytopenia: Korean experts recommendation in 2017.

Science.gov (United States)

Jang, Jun Ho; Kim, Ji Yoon; Mun, Yeung-Chul; Bang, Soo-Mee; Lim, Yeon Jung; Shin, Dong-Yeop; Choi, Young Bae; Yhim, Ho-Young; Lee, Jong Wook; Kook, Hoon

2017-12-01

Management options for patients with immune thrombocytopenia (ITP) have evolved substantially over the past decades. The American Society of Hematology published a treatment guideline for clinicians referring to the management of ITP in 2011. This evidence-based practice guideline for ITP enables the appropriate treatment of a larger proportion of patients and the maintenance of normal platelet counts. Korean authority operates a unified mandatory national health insurance system. Even though we have a uniform standard guideline enforced by insurance reimbursement, there are several unsolved issues in real practice in ITP treatment. To optimize the management of Korean ITP patients, the Korean Society of Hematology Aplastic Anemia Working Party (KSHAAWP) reviewed the consensus and the Korean data on the clinical practices of ITP therapy. Here, we report a Korean expert recommendation guide for the management of ITP.

Licensing the first nuclear power plant in the United Arab Emirates

International Nuclear Information System (INIS)

Grant, I.

2013-01-01

United Arab Emirates (UAE) has established a comprehensive legal & regulatory framework conforming to IAEA standards/guidance to regulate the nuclear sector. Federal Authority for Nuclear Regulation (FANR) is a functioning independent nuclear regulator providing controls on safety, security and non-proliferation. UAE benefits from strong international support, incl. IAEA and access to Korean organizations and practices. UAE has an active capacity building programme both human and technical. Peer reviews show UAE regulatory system is aligned with good international practices. UAE has long term commitment to develop and maintain safety culture.

Clinical Image Evaluation of Film Mammograms in Korea: Comparison with the ACR Standard

International Nuclear Information System (INIS)

Gwak, Yeon Joo; Kim, Hye Jung; Kwak, Jin Young; Son, Eun Ju; Ko, Kyung Hee; Lee, Jin Hwa; Lim, Hyo Soon; Lee, You Jin; Park, Ji Won; Shin, Kyung Min; Jang, Yun-Jin

2013-01-01

The goal of this study is to compare the overall quality of film mammograms taken according to the Korean standards with the American College of Radiology (ACR) standard for clinical image evaluation and to identify means of improving mammography quality in Korea. Four hundred and sixty eight sets of film mammograms were evaluated with respect to the Korean and ACR standards for clinical image evaluation. The pass and failure rates of mammograms were compared by medical facility types. Average scores in each category of the two standards were evaluated. Receiver operating characteristic curve analysis was used to identify an optimal Korean standard pass mark by taking the ACR standard as the reference standard. 93.6% (438/468) of mammograms passed the Korean standard, whereas only 80.1% (375/468) passed the ACR standard (p < 0.001). Non-radiologic private clinics had the lowest pass rate (88.1%: Korean standard, 71.8%: ACR standard) and the lowest total score (76.0) by the Korean standard. Average scores of positioning were lowest (19.3/29 by the Korean standard and 3.7/5 by the ACR standard). A cutoff score of 77.0 for the Korean standard was found to correspond to a pass level when the ACR standard was applied. We suggest that tighter regulations, such as, raising the Korean pass mark, subtracting more for severe deficiencies, or considering a very low scores in even a single category as failure, are needed to improve the quality of mammography in Korea

Things Korean.

Science.gov (United States)

Chang, Roberta

Presented in this booklet are brief descriptions of items and activities that are symbolic of Korean culture. Some of the items and activities described include traditional Korean clothing and accessories, dolls, fans, a Korean game called "yut," tape recordings of Korean music, a "buhk" (drum), and brass eating utensils. A map of Korea, some…

standards used for quality control of nuclear fuels

International Nuclear Information System (INIS)

Guereli, L; Can, S.

1997-01-01

Nuclear fuels and fuel materials are subject to stringent restrictions as to their quality. The standards and regulations that apply vary according to reactor type and country and the standards are stated in the quality assurance documents. The concept of quality assurance has altered the conventional quality control tests and procedures, defining which control tests are to be applied and how. Although most of the tests and measurements allow the determination of tolerances to be decided according to the agreement between the buyer and the seller, exacting procedures apply to which instruments and equipment are used for these tests and measurements, how these instruments are standardized.Detailed explanations of test methods and their documentation is a requirement in all standards. The purpose of this work is to study which standards, tests and measurements apply to the nuclear fuel production. Only the standards that apply to various stages of the nuclear fuel production (powder preparation, pellet production, fuel element and fuel assembly fabrication) are reviewed. Process and documentation control, design and licensing requirements and the frequency of inspections are quality assurance subjects. Some ASTM standards are given as examples

Nuclear powerplant standardization: light water reactors. Volume 2. Appendixes

International Nuclear Information System (INIS)

1981-06-01

This volume contains working papers written for OTA to assist in preparation of the report, NUCLEAR POWERPLANT STANDARDIZATION: LIGHT WATER REACTORS. Included in the appendixes are the following: the current state of standardization, an application of the principles of the Naval Reactors Program to commercial reactors; the NRC and standardization, impacts of nuclear powerplant standardization on public health and safety, descriptions of current control room designs and Duke Power's letter, Admiral Rickover's testimony, a history of standardization in the NRC, and details on the impact of standardization on public health and safety

Harmonization of nuclear codes and standards, pacific nuclear council working and task group report

International Nuclear Information System (INIS)

Dua, S.S.

2006-01-01

Full text: The codes and standards, both at the national and international level, have had a major impact on the industry worldwide and served it well in maintaining the performance and safety of the nuclear reactors and facilities. The codes and standards, in general, are consensus documents and do seek public input at various levels before they are finalized and rolled out for use by the nuclear vendors, consultants, utilities and regulatory bodies. However, the extensive development of prescriptive national standards if unchecked against the global environment and trade agreements (NAFTA, WTO, etc.) can also become barriers and cause difficulties to compete in the world market. During the last decade, the national and international writing standards writing bodies have recognized these issues and are moving more towards the rationalization and harmonization of their standards with the more widely accepted generic standards. The Pacific Nuclear Council (PNC) recognized the need for harmonization of the nuclear codes and standards for its member countries and formed a Task Group to achieve its objectives. The Task Group has a number of members from the PNC member countries. In 2005 PNC further raised the importance of this activity and formed a Working Group to cover a broader scope. The Working Group (WG) mandate is to identify and analyze the different codes and standards introduced to the Pacific Basin region, in order to achieve mutual understanding, harmonization and application in each country. This o requires the WG to develop and encourage the use of reasonably consistent criteria for the design and development, engineering, procurement, fabrication, construction, testing, operations, maintenance, waste management, decommissioning and the management of the commercial nuclear power plants in the Pacific Basin so as to: Promote consistent safety, quality, environmental and management standards for nuclear energy and other peaceful applications of nuclear

Test requirements for the integral effect test to simulate Korean PWR plants

Energy Technology Data Exchange (ETDEWEB)

Song, Chul Hwa; Park, C. K.; Lee, S. J.; Kwon, T. S.; Yun, B. J.; Chung, M. K

2001-02-01

In this report, the test requirements are described for the design of the integral effect test facility to simulate Korean PWR plants. Since the integral effect test facility should be designed so as to simulate various thermal hydraulic phenomena, as closely as possible, to be occurred in real plants during operation or anticipated transients, the design and operational characteristics of the reference plants (Korean Standard Nuclear Plant and Korean Next Generation Reactor)were analyzed in order to draw major components, systems, and functions to be satisfied or simulated in the test facility. The test matrix is set up by considering major safety concerns of interest and the test objectives to confirm and enhance the safety of the plants. And the analysis and prioritization of the test matrix leads to the general design requirements of the test facility. Based on the general design requirements, the design criteria is set up for the basic and detailed design of the test facility. And finally it is drawn the design requirements specific to the fluid system and measurement system of the test facility. The test requirements in this report will be used as a guideline to the scaling analysis and basic design of the test facility. The test matrix specified in this report can be modified in the stage of main testing by considering the needs of experiments and circumstances at that time.

Test requirements for the integral effect test to simulate Korean PWR plants

International Nuclear Information System (INIS)

Song, Chul Hwa; Park, C. K.; Lee, S. J.; Kwon, T. S.; Yun, B. J.; Chung, M. K.

2001-02-01

In this report, the test requirements are described for the design of the integral effect test facility to simulate Korean PWR plants. Since the integral effect test facility should be designed so as to simulate various thermal hydraulic phenomena, as closely as possible, to be occurred in real plants during operation or anticipated transients, the design and operational characteristics of the reference plants (Korean Standard Nuclear Plant and Korean Next Generation Reactor)were analyzed in order to draw major components, systems, and functions to be satisfied or simulated in the test facility. The test matrix is set up by considering major safety concerns of interest and the test objectives to confirm and enhance the safety of the plants. And the analysis and prioritization of the test matrix leads to the general design requirements of the test facility. Based on the general design requirements, the design criteria is set up for the basic and detailed design of the test facility. And finally it is drawn the design requirements specific to the fluid system and measurement system of the test facility. The test requirements in this report will be used as a guideline to the scaling analysis and basic design of the test facility. The test matrix specified in this report can be modified in the stage of main testing by considering the needs of experiments and circumstances at that time

Nuclear radiation moisture gauge calibration standard

International Nuclear Information System (INIS)

Berry, R.L.

1981-01-01

A hydrophobic standard for calibrating radiation moisture gauges is described. This standard has little or no affinity for water and accordingly will not take up or give off water under ambient conditions of fluctuating humidity in such a manner as to change the hydrogen content presented to a nuclear gauge undergoing calibration. (O.T.)

Progress in standards for nuclear air and gas treatment

International Nuclear Information System (INIS)

Burchsted, C.A.

1978-01-01

Standardization in nuclear air and gas treatment spans a period of more than 25 years, starting with military specifications for HEPA filters and filter media, and now progressing to the development of a formal code analogous to the ASME Boiler and Pressure Vessel Code. Whereas the current standard for components and installation of nuclear air cleaning systems is limited to safety related facilities for nuclear power plants, the proposed code will cover all types of critical ventilation and air and gas treatment installations for all types of nuclear facilities

Simulation of Tsunami Propagation at East Sea along the Korean Peninsula

International Nuclear Information System (INIS)

Kang, Keum Seok; Choi, Weon Hak; Kim, Chong Hak; Jin, So Beom

2005-01-01

The East Sea is one of the most vulnerable regions to unexpected Tsunami attacks in the world. Many catastrophic tsunamis have been occurred in this region. Among them, the Central East Sea tsunami occurred in 1983 has been recorded as the most devastating tsunami in modern Korean history. By employing a combined numerical model, the run-up heights of the tsunami are estimated along the Eastern coastline of the Korean Peninsula. The computed results are compared with available field measurements. A very reasonable agreement is observed. Several nuclear power plants are located along the Eastern coastline of the Korean Peninsula to get enough amount of cooling water. Furthermore, several more plants are now under construction. Generally, for the safe operation of nuclear power plants, a sea level drop may be more serious than a sea level rise. Once the water intake facilities, especially the bell mouth of a pump, are exposed above a sea water level, it will lead to the shutdown of a nuclear power plant. Sometimes the inhaled air can result in abrupt pressure surging within a mechanical cooling water system. Moreover, the ESWP (Essential Service Water Pump) is related to the safety of reactor. Thus, variation of sea level caused by tsunamis should be conservatively and accurately estimated

Face consciousness among South Korean women: a culture-specific extension of objectification theory.

Science.gov (United States)

Kim, Si Yeon; Seo, Young Seok; Baek, Keun Young

2014-01-01

This study tested key tenets of objectification theory with South Korean women and explored the roles of sexually objectifying media and culture-specific standards of beauty in body image and eating disorder symptoms. Two pilot studies with South Korean college women (n = 40, n = 30) revealed that facial characteristics such as size and shape represent a discrete variable among culture-specific standards of beauty for South Korean women. Results with a sample of 562 South Korean college women indicated that media exposure had significant positive indirect relations with body shame and eating disorder symptoms through the mediating roles of internalization, body surveillance, and face surveillance. Internalization of cultural standards of beauty had significant positive direct relations with body surveillance and face surveillance and had both direct and indirect relations with body shame and eating disorder symptoms. Body and face surveillances had significant positive direct relations with body shame and had indirect relations with eating disorder symptoms. Finally, body shame mediated the links from internalization and surveillance variables to eating disorder symptoms. The results support the applicability of objectification theory as it relates to South Korean women and point to the significance of culture-specific standards of beauty within that framework. These findings could contribute to the broader field of multicultural body image research, with potential implications for therapist practices and training. (PsycINFO Database Record (c) 2014 APA, all rights reserved).

Nuclear standards: current issues and future trends

International Nuclear Information System (INIS)

Landis, J.W.

1985-01-01

A summary of the important issues that currently face the nuclear standards field is presented and a discussion of how each of these issues is being resolved is given. The economic benefits that properly developed standards produce are listed

The North-Korean-Syrian Connection: Take It Seriously But Address It Wisely

International Nuclear Information System (INIS)

Santoro, David

2008-01-01

The release of photographs of what U.S. officials say was a Syrian nuclear reactor built with North Korean assistance (and destroyed by Israel in September 2007) could undermine the success of ongoing negotiations with Pyongyang about its nuclear weapons activities. In addition to pressing Syria to admit its nuclear ambitions, the Bush Administration argues that the disclosure of these photographs will pressure Pyongyang to honor its lagging non-proliferation commitments laid out in a six-party agreement reached in February 2007. The problem is that this could also bring current negotiations to a breakdown. In other words, in the face of U.S. confrontation, North Korean officials could simply decide to walk out of the negotiating table altogether. In the recent past, the absence of a negotiating process with Pyongyang had dramatic consequences. Following the collapse of negotiations in 2002 (when Washington confronted Pyongyang with an alleged clandestine uranium enrichment program), North Korea moved swiftly to unfreeze its plutonium production facilities, expel international inspectors, withdraw from the Nuclear Non-Proliferation Treaty (NPT), restart its reprocessing activities and, finally, conduct a nuclear test in October 2006. During this period, the possibility of war and regional proliferation increased and many proliferation experts worried that the financially strapped Communist regime would attempt to sell its nuclear technology to anyone willing to buy it, including terrorist groups. A negotiating process was finally restored with the February 2007 agreement, which the Bush Administration hailed as a major breakthrough. Nearly fifteen months down the track, Pyongyang has closed and almost entirely disabled its main nuclear reactor (Yongbyon). But it has missed key deadlines to provide detailed information on its stocks of plutonium and nuclear weapons, its uranium enrichment program as well as a complete accounting of its past proliferation activities

Development of Emergency Operating Strategies for Beyond Design Basis External Event(BDBEE)s in Korean WH Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Yoon, Duk-Joo; Lee, Seung-Chan; Sung, Je-Joong; Ha, Sang-Jun [KHNP CRI, Daejeon (Korea, Republic of); Hong, Soon-Joon; Hwang, Su-Hyun; Lee, Byung-Chul; Park, Kang-Min [FNC Tech. Co., Yongin (Korea, Republic of)

2015-10-15

Westinghouse developed and connected emergency operating procedures into a set of FLEX Support Guidelines(FSGs). This paper explains that Korean WH(Westinghouse) type nuclear power plants develop emergency operating strategies for ELAP(extended loss of all AC power), which include guidelines to use permanent and portable equipment as necessary to prevent core damage until AC power is restored from a reliable alternate source of AC power. The Korean emergency operating response strategies were developed to cope with a ELAP such as Fukushima event. The strategies include guidelines to prevent fuel damage using the FLEX equipment. Operators should take actions to prepare FLEX equipment within license basis SBO coping time. The loss of all AC power has been analyzed to identify the behavior of major NSSS process variables using RELAP computer code. The accident analysis showed that the plant does not result in fuel damage in 72 hours after an ELAP if operators take actions to cool RCS with opening of SG ADV in 5 gpm seal leak case. In this scenario, because ELAP is in process and all power cannot be used, operator should operate the FLEX equipment in order to actuate active equipment using the EOP fo SBO response. This strategy will prevent entering SAMG because this actions result in core cooling and stay in core exit temperature less than 650 .deg. C. Korean emergency operating guidelines(EOGs) will be developed using this strategies for response to the BDBEE.

Inter-Korean military confidence building after 2003.

Energy Technology Data Exchange (ETDEWEB)

Tae-woo, Kim (Korea Institute for Defense Analyses, Seoul, Republic of Korea); Littlefield, Adriane C.; Vannoni, Michael Geoffrey; Sang-beom, Kim (Korea Institute for Defense Analyses, Seoul, Republic of Korea); Koelm, Jennifer Gay; Olsen, John Norman; Myong-jin, Kim (Korea Institute for Defense Analyses, Seoul, Republic of Korea); Sung-tack, Shin (Korea Institute for Defense Analyses, Seoul, Republic of Korea)

2003-08-01

Tensions on the Korean Peninsula remain high despite a long-term strategy by South Korea to increase inter-Korean exchanges in economics, culture, sports, and other topics. This is because the process of reconciliation has rarely extended to military and security topics and those initiatives that were negotiated have been ineffective. Bilateral interactions must include actions to reduce threats and improve confidence associated with conventional military forces (land, sea, and air) as well as nuclear, chemical, and biological activities that are applicable to developing and producing weapons of mass destruction (WMD). The purpose of this project is to develop concepts for inter-Korean confidence building measures (CBMs) for military and WMD topics that South Korea could propose to the North when conditions are right. This report describes the historical and policy context for developing security-related CBMs and presents an array of bilateral options for conventional military and WMD topics within a consistent framework. The conceptual CBMs address two scenarios: (1) improved relations where construction of a peace regime becomes a full agenda item in inter-Korean dialogue, and (2) continued tense inter-Korean relations. Some measures could be proposed in the short term under current conditions, others might be implemented in a series of steps, while some require a higher level of cooperation than currently exists. To support decision making by political leaders, this research focuses on strategies and policy options and does not include technical details.

Development of nuclear power standards and relevant system in China

International Nuclear Information System (INIS)

Cao Shudong

2008-01-01

By analyzing the history of nuclear power development and the status of nuclear power codes and standards in China, the significance and necessity to quicken the development of nuclear power standards system in China are pointed out, and the guiding ideology, development thoughts, working doctrine and development objectives are put forward in this paper. (authors)

Standardization's role in revitalizing the nuclear option

International Nuclear Information System (INIS)

Ward, J.E.

1986-01-01

Considering the moribund status of the nuclear industry, something has to be done in the near-term to reverse the decaying economics of nuclear power. Standardization can turn around nuclear economics in the short term and in the longer term can foster a significant return to nuclear power. In the short term the industry needs to take advantage of those current designs that have proved their worth by excellent operating records. These designs can be replicated taking advantage of the complete status of the design and the construction techniques already in place. In the longer term it needs to develop preapproved designs and sites. Further, it must develop a discipline within the system of regulation as well as within the utility management to accept a power design as is. They cannot afford customized regulation nor customized design. Traditional institutional structures may also be up for grabs as utilities struggle to be more cost-effective. Generating companies may plan a significant role in the future of electric utilities. This kind of emphasis will also provide an impetus for the use of cost-effective, standardized designs that can be the catalyst for nuclear power's resurgence

Traveling ionospheric disturbances triggered by the 2009 North Korean underground nuclear explosion

Energy Technology Data Exchange (ETDEWEB)

Zhang, X.; Tang, L. [Wuhan Univ. (China). School of Geodesy and Geomatics

2015-04-01

Underground nuclear explosions (UNEs) can induce acoustic-gravity waves, which disturb the ionosphere and initiate traveling ionospheric disturbances (TIDs). In this paper, we employ a multi-step and multi-order numerical difference method with dual-frequency GPS data to detect ionospheric disturbances triggered by the North Korean UNE on 25 May 2009. Several International GNSS Service (IGS) stations with different distances (400 to 1200 km) from the epicenter were chosen for the experiment. The results show that there are two types of disturbances in the ionospheric disturbance series: high-frequency TIDs with periods of approximately 1 to 2 min and low-frequency waves with period spectrums of 2 to 5 min. The observed TIDs are situated around the epicenter of the UNE, and show similar features, indicating the origin of the observed disturbances is the UNE event. According to the amplitudes, periods and average propagation velocities, the high-frequency and low-frequency TIDs can be attributed to the acoustic waves in the lower ionosphere and higher ionosphere, respectively. (orig.)

[Standardization of terminology in laboratory medicine I].

Science.gov (United States)

Yoon, Soo Young; Yoon, Jong Hyun; Min, Won Ki; Lim, Hwan Sub; Song, Junghan; Chae, Seok Lae; Lee, Chang Kyu; Kwon, Jung Ah; Lee, Kap No

2007-04-01

Standardization of medical terminology is essential for data transmission between health-care institutions or clinical laboratories and for maximizing the benefits of information technology. Purpose of our study was to standardize the medical terms used in the clinical laboratory, such as test names, units, terms used in result descriptions, etc. During the first year of the study, we developed a standard database of concept names for laboratory terms, which covered the terms used in government health care centers, their branch offices, and primary health care units. Laboratory terms were collected from the electronic data interchange (EDI) codes from National Health Insurance Corporation (NHIC), Logical Observation Identifier Names and Codes (LOINC) database, community health centers and their branch offices, and clinical laboratories of representative university medical centers. For standard expression, we referred to the English-Korean/ Korean-English medical dictionary of Korean Medical Association and the rules for foreign language translation. Programs for mapping between LOINC DB and EDI code and for translating English to Korean were developed. A Korean standard laboratory terminology database containing six axial concept names such as components, property, time aspect, system (specimen), scale type, and method type was established for 7,508 test observations. Short names and a mapping table for EDI codes and Unified Medical Language System (UMLS) were added. Synonym tables for concept names, words used in the database, and six axial terms were prepared to make it easier to find the standard terminology with common terms used in the field of laboratory medicine. Here we report for the first time a Korean standard laboratory terminology database for test names, result description terms, result units covering most laboratory tests in primary healthcare centers.

Establishment of the International Nuclear Education/Training and its Cooperation Framework for Nuclear Transparency

International Nuclear Information System (INIS)

Min, B. J.; Han, K. W.; Lee, E. J.

2009-02-01

This project covered development and implementation of international nuclear education/training programs, cooperation for nuclear human resource development and education/training. provision of MS and PhD courses for qualified students from developing countries, and strengthening of infrastructure for the nuclear education/training. The WNU one week summer course was held for domestic future generation in nuclear field. NTC operated the ANENT web portal and cyber platform, supported training on their use, and prepared a KAERI-IAEA Practical Arrangement for the promotion of web-base nuclear education/training. For FNCA, an analysis was conducted on the need of nuclear education/training in South East Asian countries. The bilateral cooperation included cooperation with Vietnam. provision of Korean experience for nuclear power personnel from Egypt, and commencing of cooperation with South Africa. Also, NTC participated in GENEP for sharing Korean experience in the nuclear human resource development project. KAERI-UST MA and PhD courses with 3 foreign students started in spring 2008 and implemented. The courses were advance nuclear reactor system engineering, accelerator and nano-beam engineering, and radiation measurement science. 13 international nuclear education/training courses (IAEA, KOICA, RCARO and bilateral) were implemented for 226 foreign trainees. A reference education/training program was developed, which consisted of 15 courses that can be customized to learner levels and project stages of countries in question (e.g. Middle East. Africa). A textbook entitled 'Research Reactor Design, Management and Utilization' was developed presenting Korean experience with research reactors

Four Kilograms to Tip the Scale: China’s Exploitation of the North Korean Nuclear Crisis

Science.gov (United States)

2007-12-01

for power in East Asia. There is only ever one hegemon in the region at a time - “One mountain cannot accommodate two tigers .”35 China was the...Pyongyang by Washington 148 “Japan Downgraded With 29-year-old Woman Named Director For Asian Affairs at White ...the North Korean crisis active. Linking the Trans-Korean Railway (TKR) with the Trans- Siberian Railway (TSR) offers faster routes for Korean goods

Validation of the Korean Version of the Eating Disorder Inventory-2: Psychometric Properties and Cross-Cultural Comparison

Science.gov (United States)

Lee, Jung-Hyun; Shin, Mi-Yeon; Jo, Hye-Hyeon; Jung, Young-Chul; Kim, Joon-Ki

2012-01-01

Purpose The purpose of the present study was to examine the validity and reliability of the Korean version of the Eating Disorder Inventory-2 (EDI-2) in Korean patients with eating disorders and healthy controls, and to investigate cultural differences of EDI-2 between a Korean group and a North American standardization sample. Materials and Methods The Korean version of the EDI-2 was prepared after comprehensive clinical assessment of Korean patients with eating disorders (n=327) as well as female undergraduates (n=176). Results were compared between eating disorder subgroups (anorexia nervosa, bulimia nervosa and eating disorders not otherwise specified) and those of a North American standardization sample and healthy controls. Results The results showed that the Korean EDI-2 had adequate internal consistency (0.77-0.93) and discriminated well between patients with eating disorders and healthy controls on all subscales. Significant differences in EDI-2 subscale scores between the eating disorder groups and the healthy control group were observed; however, there was no discernible difference among the eating disorder subgroups. When compared with a North American standardization sample, the Korean control group showed significantly higher scores for drive for thinness and asceticism. When patient groups were compared, the Korean group showed significantly lower scores for perfectionism. Conclusion As expected, the results accurately reflected psychometric properties of the Korean version of EDI-2 for eating disorder patients in Korea. These findings also suggest that common characteristics for the eating disorder exist as a whole rather than with significant difference between each subgroup. In addition, significant differences between the Korean and the North American groups for both patients and controls also demonstrated specific cultural differences. PMID:23074108

Validation of the Korean version of the Eating Disorder Inventory-2: psychometric properties and cross-cultural comparison.

Science.gov (United States)

Lee, Jung-Hyun; Shin, Mi-Yeon; Jo, Hye-Hyeon; Jung, Young-Chul; Kim, Joon-Ki; Kim, Kyung Ran

2012-11-01

The purpose of the present study was to examine the validity and reliability of the Korean version of the Eating Disorder Inventory-2 (EDI-2) in Korean patients with eating disorders and healthy controls, and to investigate cultural differences of EDI-2 between a Korean group and a North American standardization sample. The Korean version of the EDI-2 was prepared after comprehensive clinical assessment of Korean patients with eating disorders (n=327) as well as female undergraduates (n=176). Results were compared between eating disorder subgroups (anorexia nervosa, bulimia nervosa and eating disorders not otherwise specified) and those of a North American standardization sample and healthy controls. The results showed that the Korean EDI-2 had adequate internal consistency (0.77-0.93) and discriminated well between patients with eating disorders and healthy controls on all subscales. Significant differences in EDI-2 subscale scores between the eating disorder groups and the healthy control group were observed; however, there was no discernible difference among the eating disorder subgroups. When compared with a North American standardization sample, the Korean control group showed significantly higher scores for drive for thinness and asceticism. When patient groups were compared, the Korean group showed significantly lower scores for perfectionism. As expected, the results accurately reflected psychometric properties of the Korean version of EDI-2 for eating disorder patients in Korea. These findings also suggest that common characteristics for the eating disorder exist as a whole rather than with significant difference between each subgroup. In addition, significant differences between the Korean and the North American groups for both patients and controls also demonstrated specific cultural differences.

Perspectives on the International and Internal Nuclear Security Regime

International Nuclear Information System (INIS)

Jang, Sung Soon

2015-01-01

The term, 'Nuclear Security' became more familiar to Korean public after the government hosted 2012 Seoul Nuclear Security Summit. Nuclear Security is prevention of, detection of and response to criminal or intentional unauthorized acts involving or directed at nuclear material, other radioactive material, associated facilities, or associated activities. Nuclear Security includes physical protection, security of radioactive sources, nuclear forensics, nuclear smuggling prevention, border monitoring, and cyber security with regard to nuclear and other radiological materials. This abstract will review recent international trends and discuss the nuclear security regime in the Republic of Korea (ROK). The international Nuclear Security Regime has been strengthened. The upcoming Chicago Summit in 2016 and the entry into force of the Amendment of Convention on Physical Protection of Nuclear Materials (CPPNM) will bring major changes in nuclear security. The Republic of Korea hosted the 2012 Seoul Summit and strengthened domestic regime to meet international standards. The ROK has worked hard to contribute to the international security regime and to establish a robust domestic security regime against terrorist threats. Even if the nuclear security regime is robust, Risk-informed Nuclear Security management should be established to meet international standards and to implement effective as well as an efficient nuclear security regime

Perspectives on the International and Internal Nuclear Security Regime

Energy Technology Data Exchange (ETDEWEB)

Jang, Sung Soon [Korea Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2015-10-15

The term, 'Nuclear Security' became more familiar to Korean public after the government hosted 2012 Seoul Nuclear Security Summit. Nuclear Security is prevention of, detection of and response to criminal or intentional unauthorized acts involving or directed at nuclear material, other radioactive material, associated facilities, or associated activities. Nuclear Security includes physical protection, security of radioactive sources, nuclear forensics, nuclear smuggling prevention, border monitoring, and cyber security with regard to nuclear and other radiological materials. This abstract will review recent international trends and discuss the nuclear security regime in the Republic of Korea (ROK). The international Nuclear Security Regime has been strengthened. The upcoming Chicago Summit in 2016 and the entry into force of the Amendment of Convention on Physical Protection of Nuclear Materials (CPPNM) will bring major changes in nuclear security. The Republic of Korea hosted the 2012 Seoul Summit and strengthened domestic regime to meet international standards. The ROK has worked hard to contribute to the international security regime and to establish a robust domestic security regime against terrorist threats. Even if the nuclear security regime is robust, Risk-informed Nuclear Security management should be established to meet international standards and to implement effective as well as an efficient nuclear security regime.

Korean/Korean American Adolescents' Responses to Young Adult Fiction and Media Created by Korean/Korean Americans

Science.gov (United States)

Kim, Eunhyun

2010-01-01

Multicultural children's and young adult literature provides readers with various opportunities: to mirror their lives and reflect the meanings of their own experiences; to gain insight on social issues as well as personal issues; and to enhance cross-cultural awareness. How might Korean/Korean American youth cope with everyday life as a minority…

Will nuclear power plant standardization reduce the licensing impact on construction

International Nuclear Information System (INIS)

Allen, J.M.; Bingham, W.G.; Keith, D.G.

1976-01-01

The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

Neutronic design and performance analysis of Korean ITER TBM by Monte Carlo method

International Nuclear Information System (INIS)

Kim, Chang Hyo; Han, Beom Seok; Park, Ho Jin

2006-01-01

The objective of this project is to develop a neutronic design of the Korean TBM(Test Blanket Module) which will be installed in ITER(International Thermonuclear Experimental Reactor). This project is intended to analyze a neutronic design and nuclear performances of the Korean ITER TBM through the transport calculation of MCCARD. In detail, we will conduct numerical experiments for developing the neutronic design of the Korean ITER TBM and improving the nuclear performances. The results of the numerical experiments produced in this project will be utilized for a design optimization of the Korean ITER TBM. In this project, we proposed the neutronic methodologies for analyzing the nuclear characteristics of the fusion blanket. In order to investigate the behavior of neutrons and photons in the fusion blanket, Monte Carlo transport calculation was conducted with MCCARD. In addition, to optimize the neutronic performances of the fusion blanket, we introduced the design concept using a graphite reflector and a Pb multiplier. Through various numerical experiments, it was verified that these design concepts can be utilized efficiently to improve neutronic performances and resolve many drawbacks. The graphite-reflected HCML blanket can provide the neutronic performances far better than the non-reflected blanket, and a slightly-enriched Li breeder can satisfy the tritium self-sufficiency. The HCSB blanket design concept with a graphite reflector and a Pb multiplier was proposed. According to results of the neutronic analyses, the graphite-reflected HCSB blanket with a Pb multiplier can provide the neutronic performances comparable with those of the conventional HCSB blanket

DOE [Department of Energy]-Nuclear Energy Standards Program annual assessment, FY 1990

International Nuclear Information System (INIS)

Williams, D.L. Jr.

1990-11-01

To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principles in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program. This report assesses the Performance Assurance Project Office (PAPO) activities in terms of the objectives of the Department of Energy-Nuclear Energy (DOE-NE) funded programs. To meet these objectives, PAPO administers a nuclear standards program and related activities and fosters the development and application of standards. This task is carried out in accordance with the principles set forth in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs, March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. 1 tab. (JF)

The role of nuclear energy for Korean long-term energy supply strategy : application of energy demand-supply model

International Nuclear Information System (INIS)

Chae, Kyu Nam

1995-02-01

An energy demand and supply analysis is carried out to establish the future nuclear energy system of Korea in the situation of environmental restriction and resource depletion. Based on the useful energy intensity concept, a long-term energy demand forecasting model FIN2USE is developed to integrate with a supply model. The energy supply optimization model MESSAGE is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Long-term demand for useful energy used as an exogeneous input of the energy supply model is derived from the trend of useful energy intensity by sectors and energy carriers. Supply-side optimization is performed for the overall energy system linked with the reactor and nuclear fuel cycle strategy. The limitation of fossil fuel resources and the CO 2 emission constraints are reflected as determinants of the future energy system. As a result of optimization of energy system using linear programming with the objective of total discounted system cost, the optimal energy system is obtained with detailed results on the nuclear sector for various scenarios. It is shown that the relative importance of nuclear energy would increase especially in the cases of CO 2 emission constraint. It is concluded that nuclear reactor strategy and fuel cycle strategy should be incorporated with national energy strategy and be changed according to environmental restriction and energy demand scenarios. It is shown that this modelling approach is suitable for a decision support system of nuclear energy policy

Adaptation in South Korean Society of North Korean Elite Defectors

Directory of Open Access Journals (Sweden)

Levi Nicolas

2017-10-01

Full Text Available This paper aims to explain the adaptation of North Korean elite defectors who fled from North Korea. Data used for the purpose of this article came from surveys of North Korean defectors conducted in the late 2000’s. Findings of the realized research indicate that the majority of senior defectors are experiencing less psychological and material issues when adjusting to society than regular North Korean defectors. The paper will proceed in three steps: explaining the notion of defectors, outlining their background, and focusing on their adaptation in South. Although defectors as a whole has emerged as of the most research group as a minority in South Korea, the so-called senior defectors have hardly been spotlighted. Basically North Korean senior defectors are supposed to strengthen the anti-Kim movement and legitimize the power of the South Korean government and the image of South Korea abroad. What has to be enlightened upon is the fact that North Korean senior defectors partially disagree with the integration policy of South Korean authorities. A major research question emerges: How are the experience of elite defectors localized in South Korea? How do their specific identities impact their opinion within the South Korean society? The aim of the article is also to categorize senior defectors and to provide in a single document a list of senior North Korea defectors based abroad. This kind of information is only available for Korean speaking readers. I wanted to make it accessible to the Englishspeaking community.

Standards for Endovascular Neurosurgical Training and Certification of the Society of Korean Endovascular Neurosurgeons 2013

Science.gov (United States)

Shin, Dong-Seong; Park, Sukh-Que; Kang, Hyun-Seung; Yoon, Seok-Mann; Cho, Jae-Hoon; Lim, Dong-Jun; Baik, Min-Woo; Kwon, O Ki

2014-01-01

The need for standard endovascular neurosurgical (ENS) training programs and certification in Korea cannot be overlooked due to the increasing number of ENS specialists and the expanding ENS field. The Society of Korean Endovascular Neurosurgeons (SKEN) Certification Committee has prepared training programs and certification since 2010, and the first certificates were issued in 2013. A task force team (TFT) was organized in August 2010 to develop training programs and certification. TFT members researched programs and systems in other countries to develop a program that best suited Korea. After 2 years, a rough draft of the ENS training and certification regulations were prepared, and the standard training program title was decided. The SKEN Certification Committee made an official announcement about the certification program in March 2013. The final certification regulations comprised three major parts: certified endovascular neurosurgeons (EN), certified ENS institutions, and certified ENS training institutions. Applications have been evaluated and the results were announced in June 2013 as follows: 126 members received EN certification and 55 hospitals became ENS-certified institutions. The SKEN has established standard ENS training programs together with a certification system, and it is expected that they will advance the field of ENS to enhance public health and safety in Korea. PMID:24851145

History of Korean Neurosurgery.

Science.gov (United States)

Hwang, Sung-nam

2015-08-01

The year 2012 was the 50th anniversary of the Korean Neurosurgical Society, and in 2013, the 15th World Congress of Neurosurgery took place in Seoul, Korea. Thus, it is an appropriate occasion to introduce the world to the history of the Korean Neurosurgical Society and the foundation, development, and growth of Korean neurosurgery. Historical materials and pictures were collected and reviewed from the history book and photo albums of the Korean Neurosurgical Society. During the last 50 years, the Korean Neurosurgical Society and Korean neurosurgery have developed and grown enormously not only in quantity but also in quality. In every aspect, the turning point from the old to the new era of the Korean Neurosurgical Society and Korean neurosurgery was the year 1980. Copyright © 2015. Published by Elsevier Inc.

Glossary of nuclear energy

International Nuclear Information System (INIS)

Seo, Du Hwan

1987-01-01

This book gives descriptions of explanations of terminologies concerning to nuclear energy such as analysis of financial safety of nuclear energy, radwaste disposal, fast breeder reactor, nuclear reactor and device, nuclear fuel and technique for concentration, using of nuclear energy radiation and measurement, plan for development of nuclear energy and international institution. This book includes 160 terms on nuclear energy and arranges in Korean alphabetical order.

Environmental monitoring standardization of effluent from nuclear fuel cycle facilities in China

International Nuclear Information System (INIS)

Gao Mili

1993-01-01

China has established some environmental monitoring standards of effluent from nuclear fuel cycle facilities. Up to date 33 standards have been issued; 10 to be issued; 11 in drafting. These standards cover sampling, gross activities measurement, analytical methods and management rules and so on. They involve with almost all nuclear fuel cycle facilities and have formed a complete standards system. By the end of the century, we attempt to draft a series of analytical and determination standards in various environmental various medium, they include 36 radionuclides from nuclear fuel cycle facilities. (3 tabs.)

Nuclear data standards - International Evaluation Co-operation volume 7

International Nuclear Information System (INIS)

Carlson, A.D.; Shibata, K.; Vonach, H.; Hambsch, F.J.; Chen, Z.; Hofmann, H.M.; Oh, S.Y.; Badikov, S.A.; Gai, E.V.; Pronyaev, V.G.; Smith, D.L.; Hale, G.M.; Kawano, T.; Larson, N.M.

2006-01-01

A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The working party determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries is organised through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by Subgroup 7, which was in charge of producing new evaluated neutron cross-section standards. When starting the project, there was a general consensus on the need to update these standards, as significant improvements had been made to the experimental database since 1991 when the last evaluation of these standards was performed. The present work was accomplished through efficient collaboration between a task force of the US Cross-section Evaluation Working Group (CSEWG), a Co-ordinated Research Project (CRP) of the International Atomic Energy Agency (IAEA) and Subgroup 7 of the Working Party on International Evaluation Co-operation (WPEC) of the NEA Nuclear Science Committee. Work is reported on the results of an international effort to evaluate the neutron cross-section standards. The evaluations include the H(n,n), 6 Li(n,t), 10 B(n,α), 10 B(n,α1γ), 197 Au(n,γ), 235 U(n,f) and 238 U(n,f) standard reactions. Evaluations were also produced for the non-standard 238 U(n,γ) and 239 Pu

Korean experiences on nuclear power technology

International Nuclear Information System (INIS)

Kim, H.; Yang, H.

1994-01-01

This paper describes the outstanding performance of the indigenous development program of nuclear power technology such as the design and fabrication of both CANDU and PWR fuel and in the design and construction of nuclear steam supply system in Korea. The success has been accomplished through the successful technology transfer from foreign suppliers and efficient utilization of R and D manpower in the design and engineering of nuclear power projects. In order to implement the technology transfer successfully, the joint design concept has been introduced along with effective on-the-job training and the transfer of design documents and computer codes. Korea's successful development of nuclear power program has resulted in rapid expansion of nuclear power generation capacity in a short time, and the nuclear power has contributed to the national economy through lowering electricity price by about 50 % as well as stabilizing electricity supply in 1980s. The nuclear power is expected to play a key role in the future electricity supply in Korea. Now Korea is under way of taking a step toward advanced nuclear technology. The national electricity system expansion plan includes 18 more units of NPPs to be constructed by the year 2006. In this circumstance, the country has fixed the national long-term nuclear R and D program (lgg2-2001) to enhance the national capability of nuclear technology. This paper also briefly describes future prospects of nuclear technology development program in Korea

ASME nuclear codes and standards: Scope of coverage and current initiatives

International Nuclear Information System (INIS)

Eisenberg, G. M.

1995-01-01

The objective of this paper is to address the broad scope of coverage of nuclear codes, standards and guides produced and administered by the American Society of Mechanical Engineers (ASME). Background information is provided regarding the evolution of the present activities. Details are provided on current initiatives intended to permit ASME to meet the needs of a changing nuclear industry on a worldwide scale. During the early years of commercial nuclear power, ASME produced a code for the construction of nuclear vessels used in the reactor coolant pressure boundary, containment and auxiliary systems. In response to industry growth, ASME Code coverage soon broadened to include rules for construction of other nuclear components, and inservice inspection of nuclear reactor coolant systems. In the years following this, the scope of ASME nuclear codes, standards and guides has been broadened significantly to include air cleaning activities for nuclear power reactors, operation and maintenance of nuclear power plants, quality assurance programs, cranes for nuclear facilities, qualification of mechanical equipment, and concrete reactor vessels and containments. ASME focuses on globalization of its codes, standards and guides by encouraging and promoting their use in the international community and by actively seeking participation of international members on its technical and supervisory committees and in accreditation activities. Details are provided on current international representation. Initiatives are underway to separate the technical requirements from administrative and enforcement requirements, to convert to hard metric units, to provide for non-U. S. materials, and to provide for translations into non-English languages. ASME activity as an accredited ISO 9000 registrar for suppliers of mechanical equipment is described. Rules are being developed for construction of containment systems for nuclear spent fuel and high-level waste transport packagings. Intensive

Key Factors for Nuclear Being Economic after Fukushima

Energy Technology Data Exchange (ETDEWEB)

Roh, Myung Sub; Park, Seo Yeon [KEPCO International Nuclear Graduate School, Ulju (Korea, Republic of)

2012-05-15

It is hard to overstate the importance of electricity to the standard of living and the quality of life in a country. Electricity demand grows with population and with the changing nature, level and composition of economic and social activity. Civilization, industrialization and urbanization are, of course, key factors. It, historically, has shown that each major nuclear accident has caused a re-examination of the risk of nuclear power leading to more stringent safety requirement and higher costs. The Fukushima accident and its likely impact on future nuclear power development are difficult to foresee. The accident was a tragedy for the people affected and seriously undermined public confidence in the safety of nuclear power. A number of countries announced reviews of their programs, some took steps toward phasing out nuclear power entirely, and others reemphasized their expansion plans. The Korean nuclear community is carry out many ambitious projects for last three decades continuously and facing the another challenges relating to the future nuclear power economics and difficulty in financing new investment. In order to meet the above economic objective, it is strongly recommended that great emphasis should be placed on maintaining the nuclear economics without jeopardizing safety such as design simplification, standardization, shortening of construction period, increased availability, etc

Key Factors for Nuclear Being Economic after Fukushima

International Nuclear Information System (INIS)

Roh, Myung Sub; Park, Seo Yeon

2012-01-01

It is hard to overstate the importance of electricity to the standard of living and the quality of life in a country. Electricity demand grows with population and with the changing nature, level and composition of economic and social activity. Civilization, industrialization and urbanization are, of course, key factors. It, historically, has shown that each major nuclear accident has caused a re-examination of the risk of nuclear power leading to more stringent safety requirement and higher costs. The Fukushima accident and its likely impact on future nuclear power development are difficult to foresee. The accident was a tragedy for the people affected and seriously undermined public confidence in the safety of nuclear power. A number of countries announced reviews of their programs, some took steps toward phasing out nuclear power entirely, and others reemphasized their expansion plans. The Korean nuclear community is carry out many ambitious projects for last three decades continuously and facing the another challenges relating to the future nuclear power economics and difficulty in financing new investment. In order to meet the above economic objective, it is strongly recommended that great emphasis should be placed on maintaining the nuclear economics without jeopardizing safety such as design simplification, standardization, shortening of construction period, increased availability, etc

Application of flow-controllable accumulator and performance analysis in Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Jung, Byung-Ryul; Lee, Un-Chul

1997-01-01

The Korean Yonggwang Nuclear Power Plants 3 ampersand 4(YGN 3 ampersand 4) are the two-loop pressurized water reactor (PWR) nuclear steam supply systems, rated at 2,815 MW(thermal). They incorporate the safety injection system (SIS) consisting of the two high pressure (HPSI) pumps, two low pressure safety injection (LPSI) pumps, and four accumulators. The SIS is two headered arrangements, each to four cold legs injection (CLI) type which provides cooling to the core in the highly unlikely event of a loss-of-coolant accident (LOCA). In the current SIS, the LPSI pumps automatically start during a LOCA, and also provide the residual heat removal capability during the shutdown cooling. This paper presents the feasibility of the removal of the LPSI from the existing SIS with minor system changes, including the increase up to four in the HPSI pumps, direct vessel injection(DVI), and the flow-controllable accumulators. A double-ended rupture of one of the four cold legs in the YGN 3 ampersand 4 was simulated using RELAP5/MOD3.1 to determine the feasibility of the application of this new SIS design to the current nuclear power plants. As a result, the calculated reflooding peak cladding surface temperature(PCT) was comparable to that of original base calculation, and the downcomer and the core collapsed liquid level during reflooding were also comparable to those in the current safety system design. This large break, cold-leg LOCA analysis addresses the reflooding capability without credit for a LPSI pump system and the applicability of the new flow-controllable accumulator. Also this analysis confirms that the combination of new flow-controllable accumulators, DVI and the increased HPSI pumps maintain the peak cladding temperature below the prescribed limits. 14 refs., 4 figs., 3 tabs

Smoking topography in Korean American and white men: preliminary findings.

Science.gov (United States)

Chung, Sangkeun; Kim, Sun S; Kini, Nisha; Fang, Hua J; Kalman, David; Ziedonis, Douglas M

2015-06-01

This is the first study of Korean Americans' smoking behavior using a topography device. Korean American men smoke at higher rates than the general U.S. Korean American and White men were compared based on standard tobacco assessment and smoking topography measures. They smoked their preferred brand of cigarettes ad libitum with a portable smoking topography device for 24 h. Compared to White men (N = 26), Korean American men (N = 27) were more likely to smoke low nicotine-yield cigarettes (p Whites. Controlling for the number of cigarettes smoked, Koreans smoked with higher average puff flows (p = 0.05), greater peak puff flows (p = 0.02), and shorter interpuff intervals (p Whites. Puff counts, puff volumes, and puff durations did not differ between the two groups. This study offers preliminary insight into unique smoking patterns among Korean American men who are likely to smoke low nicotine-yield cigarettes. We found that Korean American men compensated their lower number and low nicotine-yield cigarettes by smoking with greater puff flows and shorter interpuff intervals than White men, which may suggest exposures to similar amounts of nicotine and harmful tobacco toxins by both groups. Clinicians will need to consider in identifying and treating smokers in a mutually aggressive manner, irrespective of cigarette type and number of cigarette smoked per day.

Regulatory practices and safety standards for nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The International Symposium on Regulatory Practices and Safety Standards for Nuclear Power Plants was jointly organized by the International Atomic Energy Agency (IAEA), for Nuclear Energy Agency of the OECD and the Government of the Federal Republic of Germany with the objective of providing an international forum for the exchange of information on regulatory practices and safety standards for nuclear power plants. The Symposium was held in Munich, Federal Republic of Germany, from 7 to 10 November 1988. It was attended by 201 experts from some 32 Member States and 4 international organizations. Fifty-one papers from 19 Member States and 2 international organizations were presented and discussed in 5 technical sessions covering the following subjects: National Regulatory Practices and Safety Standards (14 papers); Implementation of Regulatory Practices - Technical Issues (8 papers); Implementation of Regulatory Practices - Operational Aspects (8 papers); Developments and Trends in Safety Standards and Practices (11 papers); International Aspects (10 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

The Canadian approach to nuclear codes and standards. A CSA forum for development of standards for CANDU: radioactive waste management and decommissioning

International Nuclear Information System (INIS)

Shin, T.; Azeez, S.; Dua, S.

2006-01-01

Together with the Canadian Standards Association (CSA), industry stakeholders, governments, and the public have developed a suite of standards for CANDU nuclear power plants that generate electricity in Canada and abroad. In this paper, we will describe: CSA's role in national and international nuclear standards development; the key issues and priority projects that the nuclear standards program has addressed; the new CSA nuclear committees and projects being established, particularly those related to waste management and decommissioning; the hierarchy of nuclear regulations, nuclear, and other standards in Canada, and how they are applied by AECL; the standards management activities; and the future trends and challenges for CSA and the nuclear community. CSA is an accredited Standards Development Organization (SDO) and part of the international standards system. CSA's Nuclear Strategic Steering Committee (NSSC) provides leadership, direction, and support for a standards committee hierarchy comprised of members from a balanced matrix of interests. The NSSC strategically focuses on industry challenges; a new nuclear regulatory system, deregulated energy markets, and industry restructuring. As the first phase of priority projects is nearing completion, the next phase of priorities is being identified. These priorities address radioactive waste management, environmental radiation management, decommissioning, structural, and seismic issues. As the CSA committees get established in the coming year, members and input will be solicited for the technical committees, subcommittees, and task forces for the following related subjects: Radioactive Waste Management; a) Dry Storage of Irradiated Fuel; b) Short-Term Radioactive Waste Management; c) Long-Term Storage and Disposal of Radioactive Waste. 2. Decommissioning Nuclear Power is highly regulated, and public scrutiny has focused Codes and Standards on public and worker safety. Licensing and regulation serves to control

Stakeholder analysis for adopting a personal health record standard in Korea.

Science.gov (United States)

Kang, Min-Jeoung; Jung, Chai Young; Kim, Soyoun; Boo, Yookyung; Lee, Yuri; Kim, Sundo

Interest in health information exchanges (HIEs) is increasing. Several countries have adopted core health data standards with appropriate strategies. This study was conducted to determine the feasibility of a continuity of care record (CCR) as the standard for an electronic version of the official transfer note and the HIE in Korean healthcare. A technical review of the CCR standard and analysis of stakeholders' views were undertaken. Transfer notes were reviewed and matched with CCR standard categories. The standard for the Korean coding system was selected. Stakeholder analysis included an online survey of members of the Korean Society of Medical Informatics, a public hearing to derive opinions of consumers, doctors, vendors, academic societies and policy makers about the policy process, and a focus group meeting with EMR vendors to determine which HIE objects were technically applicable. Data objects in the official transfer note form matched CCR standards. Korean Classification of Diseases, Korean Standard Terminology of Medicine, Electronic Data Interchange code (EDI code), Logical Observation Identifiers Names and Codes, and Korean drug codes (KD code) were recommended as the Korean coding standard.'Social history', 'payers', and 'encounters' were mostly marked as optional or unnecessary sections, and 'allergies', 'alerts', 'medication list', 'problems/diagnoses', 'results',and 'procedures' as mandatory. Unlike the US, 'social history' was considered optional and 'advance directives' mandatory.At the public hearing there was some objection from the Korean Medical Association to the HIE on legal grounds in termsof intellectual property and patients' personal information. Other groups showed positive or neutral responses. Focus group members divided CCR data objects into three phases based onpredicted adoption time in CCR: (i) immediate adoption; (ii) short-term adoption ('alerts', 'family history'); and (iii) long-term adoption ('results', 'advanced directives

Experience with nuclear safety standards development in non-governmental international organizations

International Nuclear Information System (INIS)

Becker, K.

1985-01-01

Besides the IAEA as a 'governmental' organization dealing with basic safety recommendations addressed primarily to the national regulatory bodies in developing countries, two closely related non-governmental international standards organizations have gained extensive experience in the field of nuclear standardization. Over more than 25 years since their formation, both (a) the International Organization for Standardization's (ISO) Technical Committee 85 'Nuclear Energy', in particular in its Sub-Committee 3 'Reactor Technology and Safety' and (b) the International Electrotechnical Commission's (IEC) Technical Committee 45 'Nuclear Instrumentation' have published numerous standards. A brief review is given of these, draft standards, and other documents planned to become international standards. Many of them deal with rather specialized topics typical for 'industrial' standards such as standardized procedures, instruments, methods, materials, test methods, terminology, and signs and symbols, but others are directly related to more basic safety issues. In some areas such as quality assurance, seismic aspects of siting and terminology, there has been in the past occasional overlap in the activities of the NUSS programme, IEC and ISO. Letters of Understanding have since 1981 contributed to clarifying the borderlines and to avoiding redundant efforts. Also, some experiences and problems are described arising, for example, from the harmonization of different national safety philosophies and traditions into universally accepted international standards, and the transfer of international standards into national standards systems. Finally, based on a recent comprehensive compilation of some 3300 nuclear standards and standards projects, an attempt is made to present a cost/benefit analysis and an outlook on future developments. (author)

Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Gyeong Geun; Kim, Min Chul; Yoon, Ji Hyun; Lee, Bong Sang; Lim, Sang Yeob; Kwon, Jun Hyun [Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-06-15

The transition temperature shift (TTS) of the reactor pressure vessel materials is an important factor that determines the lifetime of a nuclear power plant. The prediction of the TTS at the end of a plant’s lifespan is calculated based on the equation of Regulatory Guide 1.99 revision 2 (RG1.99/2) from the US. The fluence factor in the equation was expressed as a power function, and the exponent value was determined by the early surveillance data in the US. Recently, an advanced approach to estimate the TTS was proposed in various countries for nuclear power plants, and Korea is considering the development of a new TTS model. In this study, the TTS trend of the Korean surveillance test results was analyzed using a nonlinear regression model and a mixed-effect model based on the power function. The nonlinear regression model yielded a similar exponent as the power function in the fluence compared with RG1.99/2. The mixed-effect model had a higher value of the exponent and showed superior goodness of fit compared with the nonlinear regression model. Compared with RG1.99/2 and RG1.99/3, the mixed-effect model provided a more accurate prediction of the TTS.

Anti-nuclear activities and critics concerning nuclear power plant sites

International Nuclear Information System (INIS)

Rhee, We-Beg

2000-01-01

Korea has dynamic nuclear power expansion programs, operating 16 nuclear units producing 13710 MW in total located on 4 different sites. Last year, nuclear power supplied over 40 % of national total electricity demands. In 1998, Korean government initiated re-designation work investigating circumstance changes to rule out the unnecessary sites in consideration of a long-term power supply. Korean government has determined to expand the Ulchin site and to designate one point of Woolju county as a new candidate site, and ruled out the rest candidate sites at the end of 1998. About such a governmental measure, the two areas show different reactions. Ulchin where nuclear power plant has been operated safely for about 10 years was likely to accept the governmental determination in spite of some opposition and called for several financial supports for local development. WooIju county, however, showed a strong opposition among local environmental groups and autonomous politicians, and they presented a variety of anti-nuclear activities including demonstrations mainly at the neighbouring metropolis, Ulsan city

Reactor Physics Experiments by Korean Under-Graduate Students in Kyoto University Critical Assembly Program (KUGSiKUCA Program)

International Nuclear Information System (INIS)

Pyeon, Cheol Ho; Misawa, Tsuyoshi; Unesaki, Hironobu; Ichihara, Chihiro; Shiroya, Seiji; Whang, Joo Ho; Kim, Myung Hyun

2006-01-01

The Reactor Laboratory Course for Korean Under-Graduate Students in Kyoto University Critical Assembly (KUGSiKUCA) program has been launched from 2003, as one of international collaboration programs of Kyoto University Research Reactor Institute (KURRI). This program was suggested by Department of Nuclear Engineering, College of Advanced Technology, Kyunghee University (KHU), and was adopted by Ministry of Science and Technology of Korean Government as one of among Nuclear Human Resources Education and Training Programs. On the basis of her suggestion for KURRI, memorandum for academic corporation and exchange between KHU and KURRI was concluded on July 2003. The program has been based on the background that it is extremely difficult for any single university in Korea to have her own research or training reactor. Up to this 2006, total number of 61 Korean under-graduate school students, who have majored in nuclear engineering of Kyunghee University, Hanyang University, Seoul National University, Korea Advanced Institute of Science and Technology, Chosun University and Cheju National University in all over the Korea, has taken part in this program. In all the period, two professors and one teaching assistant on the Korean side led the students and helped their successful experiments, reports and discussions. Due to their effort, the program has succeeded in giving an effective and unique course, taking advantage of their collaboration

KWOC [Key-Word-Out-of-Context] index of nuclear energy standards

International Nuclear Information System (INIS)

Jennings, S.D.

1990-05-01

One major task of the Nuclear Standards Program funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs is to promote and support the use of standards by providing line managers and standards coordinators with data that facilitates their ability to utilize standards requirements. To meet this task, the Performance Assurance Project Office (PAPO) administers a Performance Assurance Information Program. The task is carried out in accordance with the principle set forth in DOE Order 1300.2, ''Department of Energy Standards Program,'' December 18, 1980, and DOE memorandum, ''Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs,'' March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. The purpose of this information program is to collect, compile, and distribute program-related information, reports, and publications for the benefit of the DOE-NE program participants

Daily dietary intake of elements of nutritional and radiological importance by adult Koreans

International Nuclear Information System (INIS)

Cho, S.Y.; Kang, S.H.; Lee, J.K.; Chung, Y.S.; Lee, J.Y.

2001-01-01

A one day representative mixed diet of an adult Korean was collected from the data based on the food intake of 108 healthy subjects between the ages 20 and 50. Sampling for the Korean total diet was carried out by using a market basket study based on the Korean standard food consumption scheme reported by the Korean Nutriting Society. Average consumption frequency of different food items for a one day representative mixed diet of an adult Korean and the amount of each item to prepare a one day Korean representative total diet are surveyed. The analytical methods involve both instrumental and radiochemical neutron activation techniques develop for the determination of the elements Cs, I, Sr, Th and U in various kinds of food samples. Concentrations of trace elements including 5 important elements for radiological protection, U, Th, Cs, Sr and I in the Korean total diet and the 4 most frequently consumed Korean foodstuffs have been analyzed by neutron activation analysis. Detection limits for U, Th, Sr and I were improved to ppb levels by radiochemical separation after neutron irradiation. Five biological NIST reference materials were also analyzed for quality control of the analysis. Seventeen trace elements in the Korean total diet and four Korean representative foodstuffs were also analyzed quantitatively by instrumental neutron activation analysis. (author)

Toward analytic aids for standard setting in nuclear regulation

International Nuclear Information System (INIS)

Brown, R.V.; O'Connor, M.F.; Peterson, C.R.

1979-05-01

US NRC promulgates standards for nuclear reprocessing and other facilities to safeguard against the diversion of nuclear material. Two broad tasks have been directed toward establishing performance criteria for standard settings: general-purpose modeling, and analysis specific to a particular performance criterion option. This report emphasizes work on the second task. Purpose is to provide a framework for the evaluation of such options that organizes the necessary components in a way that provides for meaningful assessments with respect to required inputs

Smoking Topography in Korean American and White Men: Preliminary Findings

Science.gov (United States)

Chung, Sangkeun; Kim, Sun S; Kini, Nisha; Fang, Hua J; Kalman, David; Ziedonis, Douglas M.

2013-01-01

Introduction This is the first study of Korean Americans’ smoking behavior using a topography device. Korean American men smoke at higher rates than the general U.S. population. Methods Korean American and White men were compared based on standard tobacco assessment and smoking topography measures. They smoked their preferred brand of cigarettes ad libitum with a portable smoking topography device for 24 hours. Results Compared to White men (N = 26), Korean American men (N = 27) were more likely to smoke low nicotine-yield cigarettes (p < 0.001) and have lower Fagerstrom nicotine dependence scores (p = 0.04). Koreans smoked fewer cigarettes with the device (p = 0.01) than Whites. Controlling for the number of cigarettes smoked, Koreans smoked with higher average puff flows (p = 0.05), greater peak puff flows (p = 0.02), and shorter interpuff intervals (p < 0.001) than Whites. Puff counts, puff volumes, and puff durations did not differ between the two groups. Conclusions This study offers preliminary insight into unique smoking patterns among Korean American men who are likely to smoke low nicotine-yield cigarettes. We found that Korean American men compensated their lower number and low nicotine-yield cigarettes by smoking more frequently with greater puff flows than White men, which may suggest exposures to similar amounts of nicotine and harmful tobacco toxins by both groups. Clinicians will need to consider in identifying and treating smokers in a mutually aggressive manner, irrespective of cigarette type and number of cigarette smoked per day. PMID:24068611

Evaluation of advanced containment features proposed to Korean SNPP

International Nuclear Information System (INIS)

Jin, Y.; Park, S.Y.; Kim, S.D.; Kim, D.H.

1997-01-01

Korean Standard Nuclear Power Plant (KSNP) has adopted many advanced design features to enhance its containment performance during severe accidents as well as to reduce changes of core damage. Robust design of containment and hydrogen mixing capability reduced containment failure probability significantly. In addition to these features, new systems are proposed for KSNP: advanced design of cavity geometry, reactor cavity flooding system, hydrogen igniter, and containment filtered venting system. Before these proposals are adopted to the KSNP, their effectiveness on containment performance has been assessed systematically. Containment event tree and sensitivity analysis are used to quantify the effectiveness of these design features. The overall results indicate that these new features do not improve the containment performance significantly except the containment filtered venting system. But adoption of the containment filtered venting system should be examined carefully because accidental failure of this system may result in undue risk to public. (author)

Nuclear safety endeavour in Korea

International Nuclear Information System (INIS)

Sang-hoon lee

1987-01-01

Korea's nuclear power plant program is growing. As it grows, nuclear safety becomes an important issue. This article traces the development of Korean nuclear power program, the structure of the nuclear industries, the Nuclear Safety Center and its roles in the regulation and licensing of nuclear power plant, and also identifies some of the activities carried out to enhance the safety of nuclear power plants. (author)

Nuclear energy dictionary

Energy Technology Data Exchange (ETDEWEB)

NONE

1978-03-15

This book is a dictionary for nuclear energy which lists the technical terms in alphabetical order. It adds four appendixes. The first appendix is about people involved with nuclear energy. The second one is a bibliography and the third one is a checklist of German, English and Korean. The last one has an index. This book gives explanations on technical terms of nuclear energy such as nuclear reaction and atomic disintegration.

Nuclear energy dictionary

International Nuclear Information System (INIS)

1978-03-01

This book is a dictionary for nuclear energy which lists the technical terms in alphabetical order. It adds four appendixes. The first appendix is about people involved with nuclear energy. The second one is a bibliography and the third one is a checklist of German, English and Korean. The last one has an index. This book gives explanations on technical terms of nuclear energy such as nuclear reaction and atomic disintegration.

Thirty years of international nuclear standards in ISO and IEC

International Nuclear Information System (INIS)

Becker, K.

1991-01-01

Of over 4700 nuclear and radiation protection standards, laws, regulations, recommendations, etc., which have been issued by 52 countries and several governmental international organizations such as IAEA, or non-government organizations such as ICRP, ICRU, ISO and IEC, more than 90% are national, and more than half of those of a non-regulatory nature. Both number and importance of international standards are, however, increasing. The two most important non-governmental international standards organizations are the International Organization for Standardization (ISO), which founded a Technical Committee (TC) 85 'Nuclear Energy' with several Sub-Committees in 1957, and the closely associated International Electrotechnical Commission (IEC) with its TC 45 'Nuclear Instrumentation' formed in 1960. There are over 20 member countries actively participating in the work in each of them, with additional observer countries and liaison to the relevant other international organizations. A brief review is given on some of the experience which has been gained by ISO/TC 85 and IEC/TC 45, and its work program and accomplishments, considering in particular recent developments. It covers nuclear safety and instrumentation, radiation protection, and the nuclear fuel cycle, as well as interface issues including definitions and terminology, interaction of the activities with the work of other national and international bodies, etc. Some problem areas are also briefly discussed. (orig.)

Nuclear power of Korea

International Nuclear Information System (INIS)

Chun Bee-Ho

2011-01-01

National nuclear is presented. Nuclear energy safety after Fukushima, international cooperation in nuclear energy is discussed. Nuclear projects with the United Arab Emirates have been developed to build 4 nuclear power plants in the UAE - APR 1400. At the Korea-Bulgaria Industrial Committee Meeting in Sofia (March 2011) Korean side proposed Nuclear Safety Training Program in Korea for Bulgarian government officials and experts transfer of know-how and profound expertise on world-class nuclear technology and nuclear safety

Standardization of nuclear power plants in the United States: recent regulatory developments

International Nuclear Information System (INIS)

Cowan, B.Z.; Tourtellotte, J.R.

1992-01-01

On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

Korean round-robin result for new international program to assess the reliability of emerging nondestructive techniques

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyung Cho; Kim, Jin Gyum; Kang, Sung Sik; Jhung, Myung Jo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2017-04-15

The Korea Institute of Nuclear Safety, as a representative organization of Korea, in February 2012 participated in an international Program to Assess the Reliability of Emerging Nondestructive Techniques initiated by the U.S. Nuclear Regulatory Commission. The goal of the Program to Assess the Reliability of Emerging Nondestructive Techniques is to investigate the performance of emerging and prospective novel nondestructive techniques to find flaws in nickel-alloy welds and base materials. In this article, Korean round-robin test results were evaluated with respect to the test blocks and various nondestructive examination techniques. The test blocks were prepared to simulate large-bore dissimilar metal welds, small-bore dissimilar metal welds, and bottom-mounted instrumentation penetration welds in nuclear power plants. Also, lessons learned from the Korean round-robin test were summarized and discussed.

Revision of the ASME nuclear quality assurance standard and its historical background

International Nuclear Information System (INIS)

Suzuki, Tetsuya

2009-01-01

ASME NQA-1-2008 'Quality Assurance Requirements for Nuclear Facility Applications' will be endorsed by US NRC by the end of 2009. This standard will apply to design, construction and operation of nuclear power plants newly erected in USA. It is important to Japanese vendors developing nuclear business in USA. Historical background, significance of revision and main revised points of the ASME nuclear quality assurance standard are described in the present paper. (T. Tanaka)

On Being There: Korean in Japan.

Science.gov (United States)

Maher, John C.; Kawanishi, Yumiko

1995-01-01

Examines the experiences of ethnic Koreans and the Korean language in Japan since 1945, focusing on Japanese attitudes toward Koreans and the Korean language, provisions for Korean and bilingual education, and the increasing influence of Koreans in Japanese society. (18 references) (MDM)

Search for adequate quality standards for neutron radiography of nuclear fuel

International Nuclear Information System (INIS)

Domanus, J.C.

1983-01-01

Unlike in other fields of industrial radiography, where standard methods and procedures are used to control the quality of the radiographic image, no such standard exists for neutron radiography of nuclear fuel. To fill that gap it was felt that standardization work ought to be started in that field, too. Accordingly in 1979 an Euratom Neutron Radiography Working Group was constituted, which initiated standardization work in the field of neutron radiography of nuclear fuel. Finding adequate standards for image quality of neutron radiographs and checking the accuracy of dimension measurements from them were given first priority. (Auth.)

Introduction to the history and current status of evidence-based korean medicine: a unique integrated system of allopathic and holistic medicine.

Science.gov (United States)

Yin, Chang Shik; Ko, Seong-Gyu

2014-01-01

Objectives. Korean medicine, an integrated allopathic and traditional medicine, has developed unique characteristics and has been active in contributing to evidence-based medicine. Recent developments in Korean medicine have not been as well disseminated as traditional Chinese medicine. This introduction to recent developments in Korean medicine will draw attention to, and facilitate, the advancement of evidence-based complementary alternative medicine (CAM). Methods and Results. The history of and recent developments in Korean medicine as evidence-based medicine are explored through discussions on the development of a national standard classification of diseases and study reports, ranging from basic research to newly developed clinical therapies. A national standard classification of diseases has been developed and revised serially into an integrated classification of Western allopathic and traditional holistic medicine disease entities. Standard disease classifications offer a starting point for the reliable gathering of evidence and provide a representative example of the unique status of evidence-based Korean medicine as an integration of Western allopathic medicine and traditional holistic medicine. Conclusions. Recent developments in evidence-based Korean medicine show a unique development in evidence-based medicine, adopting both Western allopathic and holistic traditional medicine. It is expected that Korean medicine will continue to be an important contributor to evidence-based medicine, encompassing conventional and complementary approaches.

Introduction to the History and Current Status of Evidence-Based Korean Medicine: A Unique Integrated System of Allopathic and Holistic Medicine

Directory of Open Access Journals (Sweden)

Chang Shik Yin

2014-01-01

Full Text Available Objectives. Korean medicine, an integrated allopathic and traditional medicine, has developed unique characteristics and has been active in contributing to evidence-based medicine. Recent developments in Korean medicine have not been as well disseminated as traditional Chinese medicine. This introduction to recent developments in Korean medicine will draw attention to, and facilitate, the advancement of evidence-based complementary alternative medicine (CAM. Methods and Results. The history of and recent developments in Korean medicine as evidence-based medicine are explored through discussions on the development of a national standard classification of diseases and study reports, ranging from basic research to newly developed clinical therapies. A national standard classification of diseases has been developed and revised serially into an integrated classification of Western allopathic and traditional holistic medicine disease entities. Standard disease classifications offer a starting point for the reliable gathering of evidence and provide a representative example of the unique status of evidence-based Korean medicine as an integration of Western allopathic medicine and traditional holistic medicine. Conclusions. Recent developments in evidence-based Korean medicine show a unique development in evidence-based medicine, adopting both Western allopathic and holistic traditional medicine. It is expected that Korean medicine will continue to be an important contributor to evidence-based medicine, encompassing conventional and complementary approaches.

International Nuclear Safety Experts Conclude IAEA Peer Review of Korea's Regulatory System

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of senior nuclear safety experts concluded today a two-week mission to review the regulatory framework for nuclear safety in the Republic of Korea. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Korea, while the final report will be submitted by the end of summer 2011. At the request of the Korean Government, the IAEA assembled a team of 16 senior regulatory experts from 14 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Korean Ministry for Education, Science and Technology (MEST) and the Korean Institute for Nuclear Safety (KINS). The mission is a peer-review based on the IAEA Safety Standards. ''This was the first IRRS mission organized after Japan's Fukushima Daiichi nuclear accident and it included a review of the regulatory implications of that event,' explains Denis Flory, IAEA Deputy Director General and Head of the Department of Nuclear Safety and Security. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission and Team Leader of this mission commended the Korean authorities for their openness and commitment to sharing their experience with the world's nuclear safety community. ''IRRS missions such as the one that was just concluded here in the Republic of Korea are crucial to the enhancement of nuclear safety worldwide,'' he said. The IRRS team reviewed Korea's current regulatory framework while acknowledging the fact that the country's Government has already decided to establish, as of October 2011, a new independent regulatory body to be called Nuclear Safety Commission (NSC). As a consequence, KINS role will be as a regulatory expert organization reporting to the NSC, while MEST's role will be restricted to promoting the utilization of nuclear energy. The IRRS team identified particular strengths in the Korean regulatory system

International standardization of nuclear reactor designs - the way forward

International Nuclear Information System (INIS)

Raetzke, Christian

2010-01-01

The concept of 'International Standardization of Nuclear Reactor Designs' means that vendors could build their designs in every country without having to adapt it specifically to national safety requirements. Such standardization would have two main effects. It would greatly facilitate nuclear new build worldwide by giving greater efficiency and certainty to the national licensing procedures; by taking into account the fact that vendors, and nowadays also utilities, are active across borders; by helping developing countries to establish their nuclear new build programmes; and by reducing the strain on human resources on both the regulators' and the industry's side. The second valuable effect of standardization would be to further enhance safety by improving the exchange of construction and operating experience among a number of reactors belonging to fleets of the same design. The World Nuclear Association's CORDEL (Cooperation in Reactor Design Evaluation and Licensing) Group has developed a concept for implementation of international standardization of reactor designs. It has defined a number of steps to be taken by industry. At the same time, possibilities offered by national and international regulatory mechanisms would have to be fully made use of, and some changes in regulatory frameworks might be necessary. Some steps especially towards greater cooperation of regulators have already been taken; however, much still remains to be done. The concept of deploying standardized reactor designs across a number of countries supposes an alignment and, if possible, harmonization of national safety standards; a streamlining of national licensing procedures, making them more efficient and predictable; and the willingness of national regulators to take into account licensing done in other countries. In the end, this should lead to a mutual acceptance of design approvals or, in a more distant future, even to a multinational design approval process. All in all, the concept

Consensus standards utilized and implemented for nuclear criticality safety in Japan

International Nuclear Information System (INIS)

Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka

1996-01-01

The fundamental framework for the criticality safety of nuclear fuel facilities regulations is, in many advanced countries, generally formulated so that technical standards or handbook data are utilized to support the licensing safety review and to implement its guidelines. In Japan also, adequacy of the safety design of nuclear fuel facilities is checked and reviewed on the basis of licensing safety review guides. These guides are, first, open-quotes The Basic Guides for Licensing Safety Review of Nuclear Fuel Facilities,close quotes and as its subsidiaries, open-quotes The Uranium Fuel Fabrication Facility Licensing Safety Review Guidesclose quotes and open-quotes The Reprocessing Facility Licensing Safety Review Guides.close quotes The open-quotes Nuclear Criticality Safety Handbook close-quote of Japan and the Technical Data Collection are published and utilized to supply related data and information for the licensing safety review, such as for the Rokkasho reprocessing plant. The well-established technical standards and data abroad such as those by the American Nuclear Society and the American National Standards Institute are also utilized to complement the standards in Japan. The basic principles of criticality safety control for nuclear fuel facilities in Japan are duly stipulated in the aforementioned basic guides as follows: 1. Guide 10: Criticality control for a single unit; 2. Guide 11: Criticality control for multiple units; 3. Guide 12: Consideration for a criticality accident

Technical Cybersecurity Controls for Nuclear Facilities

International Nuclear Information System (INIS)

Oh, Jinseok; Ryou, Jaecheol; Kim, Youngmi; Jeong, Choonghei

2014-01-01

To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility

Technical Cybersecurity Controls for Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Oh, Jinseok; Ryou, Jaecheol [Chungnam National Univ., Daejeon (Korea, Republic of); Kim, Youngmi; Jeong, Choonghei [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-05-15

To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility.

Standardization, diversity, and learning: A model for the nuclear power industry

International Nuclear Information System (INIS)

David, P.A.; Rothwell, G.S.

1992-11-01

The lack of standardization, frequently mentioned as a burden borne by the U.S. nuclear industry, is discussed. A simple model of learning and standardization is presented. It is shown that when the effects of learning through diversity are strong, the present value of long-run costs can be minimized with either complete standardization or with complete experimentation where no two reactors are similar in the early stages of the industry. The conclusion discusses the relevance of these and other analytical results to the present U.S. nuclear industry regarding standardization policies. 8 refs

A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

Energy Technology Data Exchange (ETDEWEB)

Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2010-05-15

Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

International Nuclear Information System (INIS)

Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon; Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub

2010-01-01

Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

Legal status of minister's notices and technology standards of 'Korea institute of nuclear safety'(KINS) to regulate nuclear safety

International Nuclear Information System (INIS)

Jung, S. K.; Jung, M. M.; Kim, S. W.; Jang, K. H.; Oh, B. J.

2003-01-01

Concerning nuclear safety or technology standards, each of 'notices' issued by minister of science and technology(MOST) empowered by law of its regulation is obviously forceful as a law, if not all. But the standards made by the chief of Korea institute of nuclear safety(KINS) to meet the tasks entrusted to KINS by MOST is only conditionally forceful as a law, that is, on the condition that law or regulation empowered the chief of KINS to make nuclear safety and/or technology standards

A study on the globalization of nuclear development

International Nuclear Information System (INIS)

Jeong, Hwan Sam; Kim, Hyun Jun

1996-05-01

Nuclear power technology in Korea has been reached at about 95 % level to self-reliance, which has developed energetically since mid of 1980s. Nowadays, it is required to set up globalization of nuclear policy to ensure the introduction of more advanced technologies and to enlarge the use of their developed technologies. In this study, prospects of nuclear power and wastes management, international safeguards, and international co-operation were analyzed focusing on the International Atomic Energy Agency to support timely the introduction of advanced technologies and assure international nuclear communities of Korean nuclear transparency in order to enhance the national policy for self-reliance on their future technology development. This study can be applied to the efficient implementation of Korean nuclear development policy and globalization policy as well. 3 tabs., 1 fig., 13 refs. (Author)

A study on the globalization of nuclear development

Energy Technology Data Exchange (ETDEWEB)

Jeong, Hwan Sam; Kim, Hyun Jun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-05-01

Nuclear power technology in Korea has been reached at about 95 % level to self-reliance, which has developed energetically since mid of 1980s. Nowadays, it is required to set up globalization of nuclear policy to ensure the introduction of more advanced technologies and to enlarge the use of their developed technologies. In this study, prospects of nuclear power and wastes management, international safeguards, and international co-operation were analyzed focusing on the International Atomic Energy Agency to support timely the introduction of advanced technologies and assure international nuclear communities of Korean nuclear transparency in order to enhance the national policy for self-reliance on their future technology development. This study can be applied to the efficient implementation of Korean nuclear development policy and globalization policy as well. 3 tabs., 1 fig., 13 refs. (Author).

Merits and difficulties in adopting codes, standards and nuclear regulations

International Nuclear Information System (INIS)

El-Saiedi, A.F.; Morsy, S.; Mariy, A.

1978-01-01

Developing countries planning for introducing nuclear power plants as a source of energy have to develop or adopt sound regulatory practices. These are necessary to help governmental authorities to assess the safety of nuclear power plants and to perform inspections needed to confirm the established safe and sound limits. The first requirement is to form an independent regulatory body capable of setting up and enforcing proper safety regulations. The formation of this body is governed by several considerations related to local conditions in the developing countries, which may not always be favourable. It is quite impractical for countries with limited experience in the nuclear power field to develop their own codes, standards and regulations required for the nuclear regulatory body to perform its tasks. A practical way is to adopt codes, standards and regulations of a well-developed country. This has merits as well as drawbacks. The latter are related to problems of personnel, software, equipment and facilities. The difficulties involved in forming a nuclear regulatory body, and the merits and difficulties in adopting foreign codes, standards and regulations required for such body to perform its tasks, are discussed in this paper. Discussions are applicable to many developing countries and particular emphasis is given to the conditions and practices in Egypt. (author)

Nuclear development in Korea

International Nuclear Information System (INIS)

Lee Byong Whi

1993-10-01

The Korean research and development project ''evelopment of Next Generation Reactor Technology'' aimed at the 21st century is briefly outlined. Activities directed to improvement of public acceptance of nuclear energy, the public information and education on the advanced nuclear reactor and fuel cycle technology are described

Economic analysis of nuclear energy

International Nuclear Information System (INIS)

Lee, Man Ki; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Song, K. D.; Oh, K. B.

2004-12-01

This study evaluated the role of nuclear energy in various aspects in order to provide a more comprehensive standard of judgement to the justification of the utilization of nuclear energy. Firstly, this study evaluated the economic value addition of nuclear power generation technology and Radio-Isotope(RI) technology quantitatively by using modified Input-Output table. Secondly, a comprehensive cost-benefit analysis of nuclear power generation was conducted with an effort to quantify the foreign exchange expenditure, the environmental damage cost during 1986-2015 for each scenario. Thirdly, the effect of the regulation of CO 2 emission on the Korean electric supply system was investigated. In more detail, an optimal composition of power plant mix by energy source was investigated, under the assumption of the CO 2 emission regulation at a certain level, by using MESSAGE model. Finally, the economic spillover effect from technology self-reliance of NSSS by Korea Atomic Energy Research Institute was evaluated. Both production spillover effect and value addition spillover effect were estimated by using Input-Output table

IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering

International Nuclear Information System (INIS)

Daughtrey, T.

1988-01-01

Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards Institute or de facto standards for programming languages

Integrated model of Korean spent fuel and high level waste disposal options - 16091

International Nuclear Information System (INIS)

Hwang, Yongsoo; Miller, Ian

2009-01-01

This paper describes an integrated model developed by the Korean Atomic Energy Research Institute (KAERI) to simulate options for disposal of spent nuclear fuel (SNF) and reprocessing products in South Korea. A companion paper (Hwang and Miller, 2009) describes a systems-level model of Korean options for spent nuclear fuel (SNF) management in the 21. century. The model addresses alternative design concepts for disposal of SNF of different types (Candu, PWR), high level waste, and fission products arising from a variety of alternative fuel cycle back ends. It uses the GoldSim software to simulate the engineered system, near-field and far-field geosphere, and biosphere, resulting in long-term dose predictions for a variety of receptor groups. The model's results allow direct comparison of alternative repository design concepts, and identification of key parameter uncertainties and contributors to receptor doses. (authors)

Korean Adoptee Identity: Adoptive and Ethnic Identity Profiles of Adopted Korean Americans

Science.gov (United States)

Beaupre, Adam J.; Reichwald, Reed; Zhou, Xiang; Raleigh, Elizabeth; Lee, Richard M.

2015-01-01

Adopted Korean adolescents face the task of grappling with their identity as Koreans and coming to terms with their adoptive status. In order to explore these dual identities, the authors conducted a person-centered study of the identity profiles of 189 adopted Korean American adolescents. Using cluster analytic procedures, the study examined…

Intercultural Usage of Mori Folium: Comparison Review from a Korean Medical Perspective

Directory of Open Access Journals (Sweden)

Byungjin Joh

2015-01-01

Full Text Available Objectives. A review on studies related to the use of Mori folium, the leaves of Morus alba, was conducted with the goal of identifying new clinical applications in Korean medicine. Methods. Global literature search was conducted using three electronic databases up to January 2015 with the term Morus alba and its Korean terms. KM literatures including textbooks and standard pharmacopoeia were separately hand-searched and reviewed to provide comparison. Data were extracted according to predetermined criteria, and clinical uses were standardized with ICD-10 categories. Results. 159 potentially relevant studies were identified, and 18 articles including 12 ethnopharmacologic and 6 clinical studies were finally included in this analysis. Ethnopharmacologic studies from 8 countries provided 17 clinical uses. We found that five out of six clinical trials were related to diabetes and suggested a moderate short-term to mild long-term effect. And 43 Korean texts also provided 156 clinical uses in 35 categories including ocular and respiratory disorders. Discussion and Conclusions. Though majority of the clinical uses were also found in Korean medicine literature, treatment of infertility, jaundice, cognitive disorder, and hyperpigmentation was found to be effective and diabetes with Morus alba was recognized to have clinical importance.

Understanding Korean food culture from Korean paintings

OpenAIRE

Hae Kyung Chung; Kyung Rhan Chung; Hung Ju Kim

2016-01-01

Background: In Korea, there are many traditional foods that have developed along with the country's rich history. In addition, various food cultures have developed through agricultural traditions, ritual ceremonies, and the sharing of affection. Paintings, works of calligraphy, and music demonstrate some of these cultural characteristics of Korean foods. Further research and analysis of Korean food culture using these data sources is currently underway. Methods: This paper focuses on the c...

The nuclear safety standards of IAEA (NUSS)

International Nuclear Information System (INIS)

Andres, H.

1980-01-01

The lecture will give an overview of the Agency's Safety Standards for Nuclear Power Plants: its range and its current state of development. The general contents of the documents will be presented, and the procedures used for their development will be briefly described. (orig.)

Korean Clinical Practice Guidelines for Aneurysmal Subarachnoid Hemorrhage

Science.gov (United States)

Cho, Won-Sang; Park, Sukh Que; Ko, Jun Kyeung; Kim, Dae-Won; Park, Jung Cheol; Yeon, Je Young; Chung, Seung Young; Chung, Joonho; Joo, Sung-Pil; Hwang, Gyojun; Kim, Deog Young; Chang, Won Hyuk; Choi, Kyu-Sun; Lee, Sung Ho; Sheen, Seung Hun; Kang, Hyun-Seung; Kim, Byung Moon; Bae, Hee-Joon; Oh, Chang Wan; Park, Hyeon Seon

2018-01-01

Despite advancements in treating ruptured cerebral aneurysms, an aneurysmal subarachnoid hemorrhage (aSAH) is still a grave cerebrovascular disease associated with a high rate of morbidity and mortality. Based on the literature published to date, worldwide academic and governmental committees have developed clinical practice guidelines (CPGs) to propose standards for disease management in order to achieve the best treatment outcomes for aSAHs. In 2013, the Korean Society of Cerebrovascular Surgeons issued a Korean version of the CPGs for aSAHs. The group researched all articles and major foreign CPGs published in English until December 2015 using several search engines. Based on these articles, levels of evidence and grades of recommendations were determined by our society as well as by other related Quality Control Committees from neurointervention, neurology and rehabilitation medicine. The Korean version of the CPGs for aSAHs includes risk factors, diagnosis, initial management, medical and surgical management to prevent rebleeding, management of delayed cerebral ischemia and vasospasm, treatment of hydrocephalus, treatment of medical complications and early rehabilitation. The CPGs are not the absolute standard but are the present reference as the evidence is still incomplete, each environment of clinical practice is different, and there is a high probability of variation in the current recommendations. The CPGs will be useful in the fields of clinical practice and research. PMID:29526058

A brief review of nuclear electronics standards . . . Past, present and future

International Nuclear Information System (INIS)

Larsen, R.S.

2000-01-01

Modular Nuclear Instrument Standards have played a key role in U. S. Department of Energy National Laboratories and similar scientific laboratories worldwide for more than three decades. The scientific and engineering efficiency and economic benefits have been well documented. Standards are constantly evolving with the introduction of new technologies and the present is a time of rapid change. This report is based on an invited talk presented at the Joint Meeting of the U.S. Nuclear Instrument Module (NIM) and European Standards for Norms in Electronics (ESONE) Standards Committees, Lyon, France, October 20, 2000. It provides a brief overview of past developments and attempts to identify areas of possible opportunities for renewed standardization efforts to meet future challenges

Crosscultural Adaptation and Validation of the Korean Version of the New Knee Society Knee Scoring System.

Science.gov (United States)

Kim, Seok Jin; Basur, Mohnish Singh; Park, Chang Kyu; Chong, Suri; Kang, Yeon Gwi; Kim, Moon Ju; Jeong, Jeong Seong; Kim, Tae Kyun

2017-06-01

The 2011 Knee Society Score © (2011 KS Score © ) is used to characterize the expectations, symptoms, physical activity, and satisfaction of patients who undergo TKA and is widely used to assess the outcome of TKA. However, it has not been adapted or validated for use in Korea. We developed a Korean version of the 2011 KS Score and evaluated the (1) test-retest reliability, (2) convergent validity, and (3) responsiveness of the Korean version. The Korean version of the 2011 KS Score was derived by using a well-established translational procedure based on international guidelines, which include translation, synthesis, back-translation, expert committee review, pretesting, and submission for appraisal. A total of 123 patients with knee osteoarthritis who were scheduled to undergo TKA were recruited for the study. Ninety percent of the patients (111 of 123) were women, which is an exact representation of the Korean population having TKAs. To evaluate reliability, the patients were evaluated twice during a 4-week interval using the questionnaire. Reliability was assessed by using intraclass correlation coefficients (ICCs) and internal consistency by using Cronbach's alpha to determine the validity of the Korean version of the 2011 KS Score. The patients were evaluated by using the validated Korean versions of the WOMAC and SF-36 questionnaires. Spearman's correlation coefficient was used for validation. Responsiveness was determined by calculating the standardized response mean from the preoperative and postoperative test scores in the Korean version of the 2011 KS Score. To address the gender disparity in our study we identified 53 males who underwent TKA for osteoarthritis after completion of this study and generated age-matched controlled groups to evaluate construct validity and responsiveness in Korean males. The reliability proved good to excellent with an ICC between 0.69 and 0.85, depending on the clinical properties tested, which included the following

The comparative study of resonance disorders for Vietnamese and Korean cleft palate speakers using nasometer.

Science.gov (United States)

Shin, Yu-Jeong; Kim, Yongsoo; Kim, Hyun-Gi

2017-12-01

Nasalance is used to evaluate the velopharyngeal incompetence in clinical diagnoses using a nasometer. The aim of this study is to find the nasalance differences between Vietnamese cleft palate children and Korean cleft palate children by measuring the nasalance of five oral vowels. Ten Vietnamese cleft palate children after surgery, three Vietnamese children for the control group, and ten Korean cleft palate children after surgery with the same age participated in this experimentation. Instead of Korean control, the standard value of Korean version of the simplified nasometric assessment procedures (kSNAP) was used. The results are as follows: (1) the highest nasalance score among the Vietnamese normal vowels is the low vowel /a/; however, that of Korean normal vowels is the high vowel /i/. (2) The average nasalance score of Korean cleft palate vowels is 18% higher than that of Vietnamese cleft palate vowels. There was a nasalance score of over 45% among the vowels /e/ and /i/ in Vietnamese cleft palate patients and /i/, /o/, and /u/ in Korean cleft palate patients. These different nasalance scores of the same vowels seem to cause an ethnic difference between Vietnamese and Korean cleft palate children.

Advanced Passive Reactors : Leading The U. S. Nuclear Renaissance

International Nuclear Information System (INIS)

Henderson, Ronald R.

1990-01-01

Twenty-one years have passed since Korea Electric Power Corporation and Westinghouse announced plans to build Kori 1. Today, Korea's nuclear program is one of the most successful in the world. The electricity generated from Kori 1 and eight other nuclear plants has helped to spark the remarkable growth and transformation of Korea into a modern industrial power. Westinghouse is proud to have been Korea's partner on six of those plants. It the past is the bast prophet of the future, then you and your countrymen should certainly be excited by your future. Korean industry is poised to continue its steady growth, and that means continued growth for your nuclear industry. Currently, the U. S. nuclear industry is experiencing a similar mood of excitement. In fact, it would be necessary to go almost all the way back to the beginning of the birth of the Korean nuclear industry, in 1969, to find a time when the future of nuclear power in the United States looked as bright as it does today. Part of our excitement stems from the welcome prospect of growth. In recent years, there has not been a market for new nuclear plants in the United States. Utilities either had excess capacity or were building plants they had ordered before 1974. For example, between 1980 and 1989, U. S. utilities completed 46 large nuclear units, but didn't order a single new one in that time. Since 1983, however, strong economic growth in the United States has caused the demand for electric power to grow about twice as fast as utilities had projected. Today, utilities will need to order new busload plants. When they do, utilities won't want technology developed 20 years ago. They'll be looking for plants that can meet the environmental, economic, and safety standards of the 21st century

American National Standards and the DOE - A cooperative effort to promote nuclear criticality safety

International Nuclear Information System (INIS)

Rothleder, B.M.

1996-01-01

The U.S. Department of Energy's (DOE's) new criticality safety order, DOE Order 420.1 (open-quotes Facility Safety,close quotes October 13, 1995), Sec. 4.3 (open-quotes Nuclear Criticality Safetyclose quotes), invokes, as an integral part, 12 appropriate American National Standards Institute/American Nuclear Society (ANSI/ANS) Series-8 standards for nuclear criticality safety, but with modifications. (The order that 420.1/4.3 replaced also invoked some ANSI/ANS Series-8 standards.) These modifications include DOE operation-specific exceptions to the standards and elaborations on some of the wording in the standards

Korean Version of Inventory of Complicated Grief Scale: Psychometric Properties in Korean Adolescents.

Science.gov (United States)

Han, Doug Hyun; Lee, Jung Jae; Moon, Duk-Soo; Cha, Myoung-Jin; Kim, Min A; Min, Seonyeong; Yang, Ji Hoon; Lee, Eun Jeong; Yoo, Seo Koo; Chung, Un-Sun

2016-01-01

We aimed to validate the Inventory of Complicated Grief (ICG)-Korean version among 1,138 Korean adolescents, representing a response rate of 57% of 1,997 students. Participants completed a set of questionnaires including demographic variables (age, sex, years of education, experience of grief), the ICG, the Children's Depression Inventory (CDI) and the Lifetime Incidence of Traumatic Events-Child (LITE-C). Exploratory factor analysis was performed to determine whether the ICG items indicated complicated grief in Korean adolescents. The internal consistency of the ICG-Korean version was Cronbach's α=0.87. The test-retest reliability for a randomly selected sample of 314 participants in 2 weeks was r=0.75 (PKaiser-Meyer-Olkin Measure of Sampling Adequacy=0.911; Bartlett's Test of Sphericity, χ(2)=13,144.7, P<0.001). After omission of 3 items, the value of Cronbach's α increased from 0.87 for the 19-item ICG-Korean version to 0.93 for the 16-item ICG-Korean version. These results suggest that the ICG is a useful tool in assessing for complicated grief in Korean adolescents. However, the 16-item version of the ICG appeared to be more valid compared to the 19-item version of the ICG. We suggest that the 16-item version of the ICG be used to screen for complicated grief in Korean adolescents.

Electromagnetic compatibility (EMC) design guidelines for I and C systems for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hwang, In Koo; Lee, Dong Young; Cha, Kyung Ho; Park, Joo Hyun; Lee, Ki Young [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-02-01

This report describes the research results on Electromagnetic Compatibility technologies for I and C(Instrumentation and Control) systems for nuclear power plants. As the nuclear industries are adopting the digital equipment rather than the conventional analog type equipment for safety I and C systems as well as non-safety systems of nuclear power plants(NPPs), it is necessary to secure compatibility against EMI(electromagnetic interference) for the digital safety I and C systems. EMI qualification, identified as a regulatory compliance item by US NRC and Korean regulatory body, should be performed in accordance with appropriate standards, because the electromagnetic environment is regarded as one of the environmental factors possible to affect the safety functions. As a technical guide on this EMI issue, this report includes description of code and standards scheme, EMI qualification methods, noise reduction strategies, and survey on noise levels in nuclear power plants. 29 refs., 72 figs., 5 tabs. (Author)

Koreans in Japan: Their Influence on Korean-Japanese Relations.

Science.gov (United States)

1979-09-01

1963. 31. The Republic of Korea National Red Cross, The Dispersed Families in Korea, Seoul, 1977. 32. Sato , Shoki, Koreans in Japan - The...1975. 34. Sumiya, Mikio , Kankoku no Keizai (The Korean Economy), Iwanami Shoten, Tokyo, Japan, 1974. 35. U.S. Government Printing Office, U.S. Army Area

Standard specification for nuclear-grade zirconium oxide powder

CERN Document Server

American Society for Testing and Materials. Philadelphia

2008-01-01

1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core. 1.2 The material described herein shall be particulate in nature. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

The north-Korean nuclear program. Round table. What do we know? What do we think we know? And what are the resulting actions?; Le programme nucleaire nord-coreen. Table ronde. Que savons-nous? Que croyons-nous savoir? Et quelles actions en resultent?

Energy Technology Data Exchange (ETDEWEB)

Pollack, J. [US Naval War College, Dept. des Recherches Strategiques, Newport (United States)

2004-06-15

The North-Korean nuclear program is problematic because of the specific government policy from which information are coming with difficulty. From open sources, the author takes stock on our knowledge concerning the military nuclear program of Pyongyang by looking on the two possible channels of nuclear matter production for nuclear weapons and on the weapons construction. He concludes on the actions to realize facing the uncertainties. (A.L.B.)

Analysis of nuclear export control system and implementing international nonproliferation regime in China

International Nuclear Information System (INIS)

Kim, J. S.; Lee, J. S.; Ahn, J. S.; Kim, B. G.; Min, K. S.

2000-01-01

China's exporting behaviour of nuclear items had been disconnected from the international non-proliferation regime such as IAEA safeguards and export control related with peaceful use of nuclear energy since 1970s. Especially, China had been one of principle suppliers of nuclear facility and technologies to Pakistan and Iran which had developed nuclear weapon programs. On the other hand, according to the rapid growth of economic scale after China began to open to the world, an active program for nuclear power plant as an electricity source had established. This means that China have surfaced as a big market to Korean nuclear industries. Regarding this, the paper dealt with the nuclear export control matters, i.e. the history of nuclear export control system and analyzed on background of enforcement of U.S.-China Nuclear Cooperation Agreement that had been apolitical issue between U.S. and China. Prospects toward conforming its nuclear export policies, laws and regulations to international standards also analyzed in results

Dictionary of nuclear energy termination

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-04-15

This book lists termination of nuclear energy such as abbreviation, symbol, unit of nuclear energy, radiological unit, the symbol for element, isotope chart and the periodic table. This book contains about 5500 words involving to nuclear energy with index in Korean and English. It arranges alphabetically. So, with this book, it is easy and fast to find out the glossary, unit and symbol on nuclear energy.

Dictionary of nuclear energy termination

International Nuclear Information System (INIS)

1983-04-01

This book lists termination of nuclear energy such as abbreviation, symbol, unit of nuclear energy, radiological unit, the symbol for element, isotope chart and the periodic table. This book contains about 5500 words involving to nuclear energy with index in Korean and English. It arranges alphabetically. So, with this book, it is easy and fast to find out the glossary, unit and symbol on nuclear energy.

Development of Tsunami PSA method for Korean NPP site

International Nuclear Information System (INIS)

Kim, Min Kyu; Choi, In Kil; Park, Jin Hee

2010-01-01

A methodology of tsunami PSA was developed in this study. A tsunami PSA consists of tsunami hazard analysis, tsunami fragility analysis and system analysis. In the case of tsunami hazard analysis, evaluation of tsunami return period is major task. For the evaluation of tsunami return period, numerical analysis and empirical method can be applied. The application of this method was applied to a nuclear power plant, Ulchin 56 NPP, which is located in the east coast of Korean peninsula. Through this study, whole tsunami PSA working procedure was established and example calculation was performed for one of real nuclear power plant in Korea

A preliminary study on the design in architecture of nuclear and radiation safety standard system

International Nuclear Information System (INIS)

Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

2014-01-01

The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

Tritium analysis of urine samples from the general Korean public.

Science.gov (United States)

Yoon, Seokwon; Ha, Wi-Ho; Lee, Seung-Sook

2013-11-01

The tritium concentrations of urine samples and the effective dose of the general Korean public were evaluated. To achieve accurate HTO analysis of urine samples, we established the optimal conditions for measuring the HTO content of urine samples. Urine samples from 50 Koreans who do not work at a nuclear facility were analyzed on the basis of the results. The average urine analysis result was 2.8 ±1 .4 Bq/L, and the range was 1.8-5.6 Bq/L. The measured values were lower than those reported for other countries. These results show that environmental factors and lifestyle differences are the main factors affecting the tritium level of the general public. © 2013 Elsevier Ltd. All rights reserved.

Principles and foundation: national standards on quantities and units in nuclear science field

International Nuclear Information System (INIS)

Chen Lishu

1993-11-01

The main contents of National Standards on Quantities and units of atomic and nuclear physics (GB 3102.9) and Quantities and Units of nuclear reactions and ionizing radiations (GB 310.10) are presented in which most important quantities with their symbols and definitions in the nuclear scientific field are given. The principles and foundation, including the International System of Units (SI) and its application to the nuclear scientific field, in the setting of the National Standards are explained

A Korean radioecology model to simulate radionuclide behavior in agricultural ecosystems following a nuclear emergency and its application to countermeasures

International Nuclear Information System (INIS)

Hwang, W.T.; Suh, K.S.; Kim, E.H.; Han, M.H.; Lee, H.S.; Lee, C.W.

2003-01-01

A Korean radioecology model to simulate radionuclide behavior in agricultural ecosystems has been developed as a module for evaluating the ingestion dose in a Korean real-time dose assessment system FADAS, which evaluates the comprehensive radiological consequences in an accidental release of radionuclides to the environment. Using the predictive results of a Korean radioecology model, a methodology for the optimization of countermeasures has been designed based on a cost-benefit analysis. In this manuscript, a Korean radioecology model including agricultural countermeasures was introduced, and discussed with the sample calculations for the postulated accidental release of radionuclides to the environment. (author)

The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

International Nuclear Information System (INIS)

Moon, Joo Hyun

2011-01-01

Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

Examination of Economic Feasibility of Nuclear Weapons in the Republic of Korea

Energy Technology Data Exchange (ETDEWEB)

Suh, Young A; Yim, Man Sung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-05-15

This observation implies that the popular view on nuclear weapons amongst Korean public is in part due to lack of knowledge about overall implications of possessing nuclear weapons. In this regard, pros and cons of nuclear weapons development need to be better characterized and understood by the public to support nuclear nonproliferation culture development. Noting lack of literature on characterizing the economics of nuclear weapons development, this study aims at performing economic feasibility analysis of nuclear weapons development in the ROK. For this purpose, an approach called Index technique based on the US experiences was applied to Korean historical data along with cost-benefit analysis and Multi-Criteria Decision Making Analysis. In this study, the scenario of nuclear weapons development against North Korean nuclear threat was compared with conventional weapons-based defense strategy. The comparison was based on cost benefit analysis and qualitative multi-criteria decision analysis. Results indicate that nuclear weapons development is not a desirable option. However, as this work was a rather simplistic academic exercise, further work is needed to support the outcome of the study. Outcome of these investigations would be useful for communication with the public regarding the need for nuclear weapons for national defense and to develop nuclear nonproliferation culture in the ROK.

Examination of Economic Feasibility of Nuclear Weapons in the Republic of Korea

International Nuclear Information System (INIS)

Suh, Young A; Yim, Man Sung

2015-01-01

This observation implies that the popular view on nuclear weapons amongst Korean public is in part due to lack of knowledge about overall implications of possessing nuclear weapons. In this regard, pros and cons of nuclear weapons development need to be better characterized and understood by the public to support nuclear nonproliferation culture development. Noting lack of literature on characterizing the economics of nuclear weapons development, this study aims at performing economic feasibility analysis of nuclear weapons development in the ROK. For this purpose, an approach called Index technique based on the US experiences was applied to Korean historical data along with cost-benefit analysis and Multi-Criteria Decision Making Analysis. In this study, the scenario of nuclear weapons development against North Korean nuclear threat was compared with conventional weapons-based defense strategy. The comparison was based on cost benefit analysis and qualitative multi-criteria decision analysis. Results indicate that nuclear weapons development is not a desirable option. However, as this work was a rather simplistic academic exercise, further work is needed to support the outcome of the study. Outcome of these investigations would be useful for communication with the public regarding the need for nuclear weapons for national defense and to develop nuclear nonproliferation culture in the ROK

A Comparison of Adaptation to Childhood Disability in Korean Immigrant and Korean Mothers.

Science.gov (United States)

Cho, Su-Je; Singer, George H. S.; Brenner, Betsy (Mary)

2003-01-01

A study examined the variables that exacerbated or buffered the impact of child problem behaviors and/or physical differences on 16 Korean mothers and 16 Korean American mothers of children with disabilities. Overall findings from data analyses were consistent with qualitative findings that Korean mothers experienced more difficulties than their…

Development of radiation shielding standards in the American Nuclear Society

International Nuclear Information System (INIS)

Trubey, D.K.

1975-11-01

The American Nuclear Society (ANS) is a standards-writing organization-member of the American National Standards Institute (ANSI). The ANS Standards Committee has a subcommittee denoted ANS-6, Shielding, whose charge is to establish standards in connection with radiation protection and shielding, to provide shielding information to other standards writing groups, and to prepare recommended sets of shielding data and test problems. This paper is a progress report of this subcommittee

Overview of the ANS [American Nuclear Society] mathematics and computation software standards

International Nuclear Information System (INIS)

Smetana, A.O.

1991-01-01

The Mathematics and Computations Division of the American Nuclear Society sponsors the ANS-10 Standards Subcommittee. This subcommittee, which is part of the ANS Standards Committee, currently maintains four ANSI/ANS software standards. These standards are: Recommended Programming Practices to Facilitate the Portability of Scientific Computer Programs, ANS-10.2; Guidelines for the Documentation of Computer Software, ANS-10.3; Guidelines for the Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry, ANS-10.4; and Guidelines for Accommodating User Needs in Computer Program Development, ANS-10.5. 5 refs

Project on standards on good behaviour for the civilian nuclear industry

International Nuclear Information System (INIS)

Strohl, Pierre; Derche, Bernard

1995-01-01

Nuclear energy has provoked complex and sometimes heated debates involving politic, economic, scientific and moral issues, objective data alongside irrational feelings, short-term calculations as well as concerns touching on the far-reaching of humanity and the earth. These debates go beyond national borders as it is obvious that even though each country may hold divergent positions regarding the development of nuclear energy, their effects have an international scope, and, therefore, must be taken into account by all nations, even those who do not operate nuclear installations. Whatever conclusion may be drawn from these debates, decisions on nuclear energy are always taken by the political authorities, almost always at the highest level, be it national or international. These political decisions then become the body of legal standards, particularly the regulations which govern how nuclear energy is used. The main standards are for technical and scientific quality, applying to energy resource needs, to the reasons why the nuclear industry should be developed, to radioprotection and nuclear security, to protection of the environment, to radioactive waste management, to information and consulting to the public, to international cooperation, to non-proliferation of atomic weapons and to physical protection of nuclear materials. (author)

Standards for psychological assessment of nuclear facility personnel. Technical report

International Nuclear Information System (INIS)

Frank, F.D.; Lindley, B.S.; Cohen, R.A.

1981-07-01

The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

Integrating Faith-based and Community-based Participatory Research Approaches to Adapt the Korean Parent Training Program.

Science.gov (United States)

Kim, Eunjung; Boutain, Doris; Kim, Sangho; Chun, Jin-Joo; Im, Hyesang

Faith and community based inquiry approaches are rarely used to develop research interventions. The purpose of this article is to present how a research team worked with six Korean American Christian churches to revise the prototype Korean Parent Training Program (KPTP), based upon the Bright Futures Parenting Program. The collaboration was sought to better integrate and align the KPTP with Korean culture and faith. The KPTP was developed to promote positive parenting practices and decrease mental health disparities of Korean American children. Sixteen church participants completed a Delphi survey, a workshop series, Community Theaters, and focus groups. The participants suggested adding Korean traditional parenting virtues, Christian parenting principles, and revising the standardized parent training and program philosophy. Revisions made KPTP sensitive to Korean culture and faith, and promoted program acceptability. The process demonstrated the importance of working with church volunteers to develop faith-based and community-based health promotion interventions targeting Korean American faith communities. This research presents significant and meaningful implications for working with other faith communities from minority backgrounds. Copyright © 2017 Elsevier Inc. All rights reserved.

Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

International Nuclear Information System (INIS)

2005-07-01

The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

Report on ANSI/ASME nuclear air and gas treatment standards for nuclear power plants

International Nuclear Information System (INIS)

Fish, J.F.

1979-01-01

Original N Committee, N45-8, has completed and published through the approved American National Standards Institute process two Standards, N-509 and N-510. This committee has been dissolved and replaced by ASME Committee on Nuclear Air and Gas Treatment with expanded scope to cover not only air cleaning, but thermal treatment equipment. Current efforts are directed to produce Code documents rather than Standards type publications. This report summarizes changed scope, current organization and sub-committee coverage areas

Korean Screen Cultures

DEFF Research Database (Denmark)

Screen Cultures sets out to redress this imbalance with a broad selection of essays spanning both North and South as well as different methodological approaches, from ethnographic and audience studies to cultural materialist readings. The first section of the book, «The South», highlights popular media...... new approaches to Korean popular culture beyond national borders and includes work on K-pop and Korean television drama. This book is a vital addition to existing scholarship on Korean popular culture, offering a unique view by providing an imaginary unification of the two Koreas negotiated through...

Standard Specification for Nuclear Grade Zirconium Oxide Pellets

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

A feasibility study on the longer cycle operation of Yonggwang nuclear power plants 3 and 4 (3 rd quarter report)

Energy Technology Data Exchange (ETDEWEB)

Zee Sung Kyun; Song, Jae Woong; Ha, Young Joon; Kim, Kyu Tae [Korea Advanced Institute of Science and Technolgoy, Taejon (Korea, Republic of)

1996-04-01

In this report, described are results of the feasibility study on applying for the 18-month cycle in Korean Standard Nuclear Power Plants (KSNPs). This report contains results of safety and economic evaluations, radiation source analysis, an effect on changing the calibration period for each component of NSSS, and review on the related regulating codes. 12 refs., 34 tabs., 28 figs. (author)

A nuclear standard high-efficiency adsorber for iodine

International Nuclear Information System (INIS)

Wang Jianmin; Qian Yinge

1988-08-01

The structure of a nuclear standard high-efficiency adsorber, adsorbent and its performance are introduced. The performance and structure were compared with the same kind product of other firms. The results show that the leakage rate is less than 0.005%

States and tendencies of German standards in the field of nuclear filter technology

International Nuclear Information System (INIS)

Fichtner, N.; Sinhuber, D.

1977-01-01

The current situation in the Federal Republic of Germany with regard to standards and guidelines in the field of filter technology, as they apply to nuclear technology, is first presented. A detailed discussion follows of the results arrived at by the Nuclear Technology Standards Committee in its deliberations on the Standards' project DIN 25 414 'Ventilation equipment in nuclear power stations'. Particular attention is paid to the technical safety requirements for particulate filters, filter casings and filter housings, and methods of testing. The results so far obtained as regards filters in ventilation plant for pressurized water reactors are also dealt with

Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

Development of EDG Engine Condition Diagnosis Logic in Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Byoung Oh; Choi, Kwang Hee; Lee, Sang Guk

2012-01-01

Through benchmarking using the excellent record of the nuclear power plants under operation in the United States and Europe and with the continuous development of nuclear-related technology, the Korea Hydro and Nuclear Power Co., LTD (KHNP) reached an average planned preventive maintenance period of 29.6 days in 2009. In addition, KHNP plans to reduce the planned preventive maintenance period at Korea standard nuclear plants (KSNPs) from 29.6 days to less than 21 days by 2014 through a combination of domestic research and development (R and D) and the introduction of the technical know-how applied in the very best overseas nuclear power plants (NPPs). Accordingly, it is necessary to reduce the inspection and maintenance periods of an emergency diesel generator (EDG), which are currently set in the planned preventive maintenance period. If the condition-based predictive maintenance (CBM) technology is applied to EDG engines, the maintenance period of an EDG will be shortened because engine maintenance is accomplished according to the engine condition under this plan. In this study, in the series of CBM program developments which will be applied to EDG engines, the development results of condition diagnosis logic to be applied to EDG engines for exiting domestic NPPs are introduced

Survey of Regulations Applicable to the Finned Containment in Korean Nuclear Power Plant for Light Water Reactor

International Nuclear Information System (INIS)

Noh, Hyung Gyun; Kang, Hie Chan

2016-01-01

In severe accident, the molten corium would discharge into the reactor cavity and interact with water and concrete of cavity. Molten corium includes non-oxidation metals such as Zr, Fe and Cr. These metal species reacted with water emit hydrogen gas. In addition to this, a mount of steam can be emitted to the containment such as steam line break accident. As a result, steam and hydrogen gas can pressurize containment over the design pressure and threaten its integrity. For this reasons, a concept equipped with finned on the containment building was proposed for coping with prolonged accident. Finned containment can enhance heat transfer to the ambient, and the building itself is working as a heat sink. Multiple metal fins and metal rod are penetrated into containment wall, and the rods are working as an additional path of heat removal. To be accepted in the nuclear power plants, this configuration should satisfy the requirement of heat removal and follow all regulations related with containment also. For applying to Korean nuclear power plants, the finned containment should follow all regulations specialized in Korea such as Nuclear regulatory criteria for light water reactor and Guidelines of nuclear safety examination for light water reactor. A concept of containment as a passive cooling system has been proposed. Furthermore, the new containment concept can be applied on the real containment which satisfies the various regulations. Finned containment would be expected positive effects on heat removal from the containment. If the fins are properly welded to the liner, finned containment could satisfy the leak tightness and prevention of external influences. Finned containment could be favorable to protect external impact like aircraft crash because of the additional structural integrity by the fins

Survey of Regulations Applicable to the Finned Containment in Korean Nuclear Power Plant for Light Water Reactor

Energy Technology Data Exchange (ETDEWEB)

Noh, Hyung Gyun [Pohang University, Pohang (Korea, Republic of); Kang, Hie Chan [Kunsan University, Gunsan (Korea, Republic of)

2016-05-15

In severe accident, the molten corium would discharge into the reactor cavity and interact with water and concrete of cavity. Molten corium includes non-oxidation metals such as Zr, Fe and Cr. These metal species reacted with water emit hydrogen gas. In addition to this, a mount of steam can be emitted to the containment such as steam line break accident. As a result, steam and hydrogen gas can pressurize containment over the design pressure and threaten its integrity. For this reasons, a concept equipped with finned on the containment building was proposed for coping with prolonged accident. Finned containment can enhance heat transfer to the ambient, and the building itself is working as a heat sink. Multiple metal fins and metal rod are penetrated into containment wall, and the rods are working as an additional path of heat removal. To be accepted in the nuclear power plants, this configuration should satisfy the requirement of heat removal and follow all regulations related with containment also. For applying to Korean nuclear power plants, the finned containment should follow all regulations specialized in Korea such as Nuclear regulatory criteria for light water reactor and Guidelines of nuclear safety examination for light water reactor. A concept of containment as a passive cooling system has been proposed. Furthermore, the new containment concept can be applied on the real containment which satisfies the various regulations. Finned containment would be expected positive effects on heat removal from the containment. If the fins are properly welded to the liner, finned containment could satisfy the leak tightness and prevention of external influences. Finned containment could be favorable to protect external impact like aircraft crash because of the additional structural integrity by the fins.

Standards: An international framework for nuclear safety

International Nuclear Information System (INIS)

Versteeg, J.

2000-01-01

The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Mostaza, J. M.

2011-07-01

Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

Nuclear design report for Yonggwang nuclear power plant unit 3 cycle 2

Energy Technology Data Exchange (ETDEWEB)

Zee, Sung Kyun; Song, Jae Woong; Song, Jae Seung; Park, Sang Yoon; Yoo, Choon Sung; Baek, Byung Chan; Ryu, Hyo Sang; Park, Jin Ha; Cho, Young Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-01-01

This report presents nuclear design calculations for Cycle 2 of Yonggwang Unit 3. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths, and operational limits. In addition, the report contains necessary data for the startup tests and for the assurance of shutdown margin during reactor operation. The reload core consists of 48 fresh Korean Standard Fuel Assemblies (KSFAs)and 129 burned KSFAs. Among the 48 fresh KSFAs, 32 fuel assemblies contain burnable poison rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 2 amounts to 276 EFPD corresponding to a cycle burnup of 10,160 MWD/MTU. 95 figs., 31 tabs., 7 refs. (Author) .new.

Principles and standards of nuclear safety and their implementation

International Nuclear Information System (INIS)

Franzen, L.F.

1979-01-01

Nuclear safety starts with the design of a nuclear facility and is only completed with its decommissioning. In the various phases of a nuclear facility's lifetime, safety evaluations are required. The licensing prerequisites for construction, operation, modification, decommissioning are based on elements of the relevant national legislation and related ordinances as well as on international regulations. They should be expanded by a system of criteria and standards spelling out the proven practice as developed over the last decades in the industrialized countries and by international organizations such IAEA with its safety codes and guides. (NEA) [fr

Nuclear characteristics analysis report for system-integrated modular advanced reactor

Energy Technology Data Exchange (ETDEWEB)

Park, Sang Yoon; Lee, Chung Chan; Song, Jae Seung; Cho, Byung Oh; Zee, Sung Quun

1998-11-01

This report present nuclear characteristics analysis results for SMART. Information is given on fuel loading, power density distributions, reactivity coefficients and control rod worths. The core consists of 57 modified Korean Standard Fuel Assemblies (m-KOFAs), and all fuel assemblies contain burnable absorbers to control the power distribution and the excess reactivity that is required for soluble boron-free and ultra longer cycle operation. The cycle length of SMART amounts to 990 EFPD corresponding to a cycle burnup of 26,250 MWD/MTU. (author). 4 refs., 6 tabs., 85 figs.

Nuclear characteristics analysis report for system-integrated modular advanced reactor

International Nuclear Information System (INIS)

Park, Sang Yoon; Lee, Chung Chan; Song, Jae Seung; Cho, Byung Oh; Zee, Sung Quun

1998-11-01

This report present nuclear characteristics analysis results for SMART. Information is given on fuel loading, power density distributions, reactivity coefficients and control rod worths. The core consists of 57 modified Korean Standard Fuel Assemblies (m-KOFAs), and all fuel assemblies contain burnable absorbers to control the power distribution and the excess reactivity that is required for soluble boron-free and ultra longer cycle operation. The cycle length of SMART amounts to 990 EFPD corresponding to a cycle burnup of 26,250 MWD/MTU. (author). 4 refs., 6 tabs., 85 figs

Development of the Korean framework for senior-friendly hospitals: a Delphi study.

Science.gov (United States)

Kim, Yoon-Sook; Han, Seol-Heui; Hwang, Jeong-Hae; Park, Jae-Min; Lee, Jongmin; Choi, Jaekyung; Moon, Yeonsil; Kim, Hee Joung; Shin, Grace Jung Eun; Lee, Ji-Sun; Choi, Ye Ji; Uhm, Kyeong Eun; Kim, In Ae; Nam, Ji-Won

2017-08-04

Aging is an inevitable part of life. One can maintain well-being and wellness even after discharge and/or transition if his or her functional decline is minimized, sudden decline is prevented, and functioning is promoted during hospitalization. Caring appropriately for elderly patients requires the systematic application of Senior-Friendly Hospital principles to all operating systems, including medical centres' organization and environment, as well as patient treatment processes. The Senior-Friendly Hospital framework is valid and important for patient safety and quality improvement. This study aimed to make recommendations regarding the development of the Korean Framework for Senior-Friendly Hospitals for older patients' care management, patient safety interventions, and health promotion, via a Delphi survey. Two rounds of Delphi surveying were conducted with 15 participants who had at least 3 years' experience in accreditation surveying and medical accreditation standards, survey methods, and accreditation investigator education. In each round, we calculated statistics describing each standard's validity and feasibility. The Korean Framework for Senior-Friendly Hospitals included 4 Chapters, 11 categories, and 67 standards through consensus of the Senior-Friendly Hospitals task force and experts' peer review. After the two rounds of Delphi surveying, validity evaluation led to no changes in standards of the Senior-Friendly Hospitals; however, the number of standards showing adequate validity decreased from 67 to 58. Regarding feasibility, no changes were necessary in the standards; however, the number of categories showing adequate feasibility decreased from 11 to 8 and from 67 to 30, respectively. The excluded categories were 3.2, 4.2, and 4.3 (service, transportation, and signage and identification). The highest feasibility values were given to standards 2.1.1, 4.1.4, and 4.1.6. The highest feasibility score was given to standard 2.4.2. The Korean Framework for

The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

Energy Technology Data Exchange (ETDEWEB)

Moon, Joo Hyun [Dongguk Univ., Gyeongbuk (Korea, Republic of)

2011-07-15

Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

Technical requirements for the ASME PRA standard for nuclear power plant applications

International Nuclear Information System (INIS)

Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

2000-01-01

In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

Nuclear Power in Korea

International Nuclear Information System (INIS)

Ha, Duk-Sang

2009-01-01

Full text: Korea's nuclear power program has been promoted by step-by-step approach; the first stage was 1970's when it depended on the foreign contractors' technology and the second was 1980's when it accumulated lots of technology and experience by jointly implementing the project. Lastly in the third stage in 1990's, Korea successfully achieved the nuclear power technological self-reliance and developed its standard nuclear power plant, so-called Optimized Power Reactor 1000 (OPR 1000). Following the development of OPR 1000, Korea has continued to upgrade the design, known as the Advanced Power Reactor 1400 (APR 1400) and APR+. Korea is one of the countries which continuously developed the nuclear power plant projects during the last 30 years while the other advanced countries ceased the project, and therefore, significant reduction of project cost and construction schedule were possible which benefits from the repetition of construction project. And now, its nuclear industry infrastructure possesses the strong competitiveness in this field.The electricity produced from the nuclear power is 150,958 MWh in 2008, which covers approximately 36% of the total electricity demand in Korea, while the installed capacity of nuclear power is 17,716 MW which is 24% of the total installed capacity. We are currently operating 20 units of nuclear power plants in Korea, and also are constructing 8 additional units (9,600 MW). Korea's nuclear power plants have displayed their excellent operating performance; the average plant capacity factor was 93.4% in 2008, which are about 15% higher than the world average of 77.8%. Moreover, the number of unplanned trips per unit was only 0.35 in 2008, which is the world top class performance. Also currently we are operating four CANDU nuclear units in Korea which are the same reactor type and capacity as the Cernavoda Units. They have been showing the excellent operating performance, of which capacity in 2008 is 92.8%. All the Korean

Research on the management and endorsement of nuclear safety standards in the United States and its revelation for China

Science.gov (United States)

Liu, Ting; Tian, Yu; Yang, Lili; Gao, Siyi; Song, Dahu

2018-01-01

This paper introduces the American standard system, the Nuclear Regulatory Commission (NRC)’s responsibility, NRC nuclear safety regulations and standards system, studies on NRC’s standards management and endorsement mode, analyzes the characteristics of NRC standards endorsement management, and points out its disadvantages. This paper draws revelation from the standard management and endorsement model of NRC and points suggestion to China’s nuclear and radiation safety standards management.The issue of the “Nuclear Safety Law”plays an important role in China’s nuclear and radiation safety supervision. Nuclear and radiation safety regulations and standards are strong grips on the implementation of “Nuclear Safety Law”. This paper refers on the experience of international advanced countriy, will effectively promote the improvement of the endorsed management of China’s nuclear and radiation safety standards.

Regulatory Endorsement Activities for ASME Nuclear Codes and Standards

International Nuclear Information System (INIS)

West, Raymond A.

2006-01-01

The ASME Board on Nuclear Codes and Standards (BNCS) has formed a Task Group on Regulatory Endorsement (TG-RE) that is currently in discussions with the United States Nuclear Regulatory Commission (NRC) to look at suggestions and recommendations that can be used to help with the endorsement of new and revised ASME Nuclear Codes and Standards (NC and S). With the coming of new reactors in the USA in the very near future we need to look at both the regulations and all the ASME NC and S to determine where we need to make changes to support these new plants. At the same time it is important that we maintain our operating plants while addressing ageing management needs of our existing reactors. This is going to take new thinking, time, resources, and money. For all this to take place the regulations and requirements that we use must be clear concise and necessary for safety and to that end both the NRC and ASME are working together to make this happen. Because of the influence that the USA has in the world in dealing with these issues, this paper is written to inform the international nuclear engineering community about the issues and what actions are being addressed under this effort. (author)

Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

International Nuclear Information System (INIS)

Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S.

2007-12-01

Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result

Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

Energy Technology Data Exchange (ETDEWEB)

Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S

2007-12-15

Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result.

Comparison of ISO 9000 and recent software life cycle standards to nuclear regulatory review guidance

International Nuclear Information System (INIS)

Preckshot, G.G.; Scott, J.A.

1998-01-01

Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the assessment of certain quality and software life cycle standards to determine whether additional guidance for the U.S. nuclear regulatory context should be derived from the standards. This report describes the nature of the standards and compares the guidance of the standards to that of the recently updated Standard Review Plan

Seismic design standardization of nuclear facilities

International Nuclear Information System (INIS)

Reddy, G.R.; Vaze, K.K.

2011-01-01

Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

Referring to IAEA system to improve Chinese standards system on nuclear and radiation safety

International Nuclear Information System (INIS)

Shang Zhaorong; Wang Wenhai

2010-01-01

Referring to the standards system of IAEA, to build and improve the Chinese standards system of nuclear and radiation safety is a long term infrastructure work and an assurance to keep sustainable development of nuclear industry and nuclear technology application in China. The paper analyses the current main problem, and gives some suggestions on developing and improving the system. (authors)

Nuclear anapole moment and tests of the standard model

International Nuclear Information System (INIS)

Flambaum, V. V.

1999-01-01

There are two sources of parity nonconservation (PNC) in atoms: the electron-nucleus weak interaction and the magnetic interaction of electrons with the nuclear anapole moment. A nuclear anapole moment has recently been observed. This is the first discovery of an electromagnetic moment violating fundamental symmetries--the anapole moment violates parity and charge-conjugation invariance. We describe the anapole moment and how it can be produced. The anapole moment creates a circular magnetic field inside the nucleus. The interesting point is that measurements of the anapole allow one to study parity violation inside the nucleus through atomic experiments. We use the experimental result for the nuclear anapole moment of 133 Cs to find the strengths of the parity violating proton-nucleus and meson-nucleon forces. Measurements of the weak charge characterizing the strength of the electron-nucleon weak interaction provide tests of the Standard Model and a way of searching for new physics beyond the Standard Model. Atomic experiments give limits on the extra Z-boson, leptoquarks, composite fermions, and radiative corrections produced by particles that are predicted by new theories. The weak charge and nuclear anapole moment can be measured in the same experiment. The weak charge gives the mean value of the PNC effect while the anapole gives the difference of the PNC effects for the different hyperfine components of an electromagnetic transition. The interaction between atomic electrons and the nuclear anapole moment may be called the ''PNC hyperfine interaction.''

The effect of severe accident mitigation design on the containment performance for Korean ALWR

International Nuclear Information System (INIS)

Na, J. H.; Lee, J. S.; Lim, H. K.; Kim, J. K.

2001-01-01

The containment performance analysis for Korean ALWR standard design has been performed to confirm the safety goal and to identify the design features vulnerable to severe accidents for the on-going design. The results in terms of conditional containment failure probability show Korean ALWR design does not have any particular vulnerability given core damage sequences. It shows the conditional containment failure probability for pull power internal event is less than that of design goal. The late containment failure is much less than 4% for given core damages and that of containment bypass is about 2%. New design features of the Korean ALWR such as bydrogen mitigation system (IIMS), cavity flooding system (CFS), and emergency containment spray bakcup system (ECSBS), external reactor vessel cooling (ERVC), etc. are reflected in Korean ALWR design and is reviewed in this paper to give an insight for the design vulnerabilities and input to the development of accident management. These Korean ALWR specific design features showed the containment performance is significantly enhanced compared with the other PWR plants

Characterization of a metallic mechanical standard junction for a specific nuclear application

International Nuclear Information System (INIS)

Villanueva, Jose; Miller, Marcelo E.; Vazquez, Luis; Halpert, Silvia

2007-01-01

A testing procedure, targeted to promote that an industrial standard component can be used in a nuclear particular application, is designed and applied. Namely, a mechanical standard junction component, that is widely recognized for its industrial reliability, is commonly used to fit two stainless steel tubes, is intended to be used in a particular nuclear application fitting a stainless steel tube to a Zircaloy-4 tube counterpart. The junction will be subjected to pressure and temperature typical of primary circuit coolant in a nuclear power plant. The results found once the test was applied (catastrophic fault and significant water leakage absence) allow to advice using this mechanical junction device as a valid nuclear design option fitting the proposed tubes. (author) [es

Historic Factors Influencing Korean Higher Education. Korean Studies Series, No. 17.

Science.gov (United States)

Jeong-kyu, Lee

This book examines the religious and philosophical factors historically affecting Korean higher education, and the characteristics of contemporary Korean higher education in relation to organizational structure, leadership, and organizational culture. The book is organized into 4 parts, with 11 chapters. Part One focuses on identifying the problem…

The latest dictionary of nuclear energy term

International Nuclear Information System (INIS)

1996-06-01

This book is the latest dictionary of nuclear energy term. It deals with explanations of nuclear energy term in alphabetical order. It also lists abbreviation of nuclear energy term. This book contains symbol and unit, radiation units, greek letters, the symbol of for element, the table of an isotope and the periodic table on nuclear power term. It includes glossary of nuclear power in Korean and French and conceptual map about development of nuclear power.

Physical protection system to detect and control the illicit trafficking and transfer of nuclear materials in Korea

Energy Technology Data Exchange (ETDEWEB)

Cho, Young Ho [Catholic Univ. of Daegu, Gyeongbuk (Korea, Republic of); Moon, Joo Hyun [Dongguk Univ., Gyeongbuk (Korea, Republic of)

2011-11-15

Physical protection has played an essential role in ensuring the implementation of global nuclear nonproliferation framework for the past decades. Since the 9/11 terrorist attacks upon the United States, physical protection has also played the same role in combating nuclear terrorism. Nowadays, physical protection is more highlighted than before with global nuclear security regimes more strengthened. Ever since the commencement of the first nuclear power plant in 1978, Korea has devotedly implemented international physical protection standards as an exemplary country in respect of the peaceful use of nuclear energy. The Korean government has recently reinforced national physical protection policy including the revision of laws and regulations. In this paper, the national policy is extensively reviewed and additional measures are proposed to enhance the national physical protection system. (orig.)

Update to nuclear data standards for nuclear measurements. Summary report of a consultants' meeting

International Nuclear Information System (INIS)

Wienke, H.; Chiba, S.; Hambsch, F.J.; Olsson, N.; Smirnov, A.N.

1997-05-01

This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the 10 B(n,α) reaction in the energy region below 20 Mev; and the H(n,n), 235 U9(n,f), 238 U(n,f), and 209 Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs

The IAEA safety standards for radiation, waste and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, Abel J.

1997-01-01

This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

Korean opera-film Chunhyang and the trans-cultural politics of the voice

Directory of Open Access Journals (Sweden)

Joe Jeongwon

2005-01-01

Full Text Available This essay examines a Korean opera-film Chunhyang (2000 to show how it departs from the standard practice of Western opera-film and how its uniqueness is generated by the characteristics of indigenous Korean opera P'ansori. In spite of its uniqueness, however, Chunhyang shows its affinities with its Western sisters by confirming what has been criticized by many feminist scholars as one of the most serious problems in the Western tradition of cinema, especially Hollywood's classical films: namely, the gendered politics of the voice.

Nuclear program of South Korea

International Nuclear Information System (INIS)

Brown, D.S.; James, K.R.

1993-01-01

Slightly larger than Portugal, South Korea comprises the lower half on the Korean Peninsula, covering approximately 38 thousand square miles. the Republic of Korea (South Korea) was established in 1948, and until 1962 the country grew slowly. However, through a series of five-year economic plans initiated by South Korean President Park Ching Hee, South Korea has since created an export-oriented economy, which now plays a major role in regional as well as global trade. South Korea has been forced to constantly upgrade its power generation structure in order to sustain the explosive growth it has experienced. Nuclear power has been a major player in this expansion and is expected to play an ever-increasing role. The country presently operates nine nuclear reactors with a total net generating capacity of 7,266 MWe. By the year 2006, the nuclear program is scheduled to grow to 27 reactors, with a net generating capacity exceeding 23 thousand MWe. Once this goal is reached, nuclear-generated power would account for more than 40 percent of the country's total installed electrical capacity

Globalization of ASME Nuclear Codes and Standards

International Nuclear Information System (INIS)

Swayne, Rick; Erler, Bryan A.

2006-01-01

With the globalization of the nuclear industry, it is clear that the reactor suppliers are based in many countries around the world (such as United States, France, Japan, Canada, South Korea, South Africa) and they will be marketing their reactors to many countries around the world (such as US, China, South Korea, France, Canada, Finland, Taiwan). They will also be fabricating their components in many different countries around the world. With this situation, it is clear that the requirements of ASME Nuclear Codes and Standards need to be adjusted to accommodate the regulations, fabricating processes, and technology of various countries around the world. It is also very important for the American Society of Mechanical Engineers (ASME) to be able to assure that products meeting the applicable ASME Code requirements will provide the same level of safety and quality assurance as those products currently fabricated under the ASME accreditation process. To do this, many countries are in the process of establishing or changing their regulations, and it is important for ASME to interface with the appropriate organizations in those countries, in order to ensure there is effective use of ASME Codes and standards around the world. (authors)

An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

International Nuclear Information System (INIS)

Warren, C.C.

2010-01-01

Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

Energy Technology Data Exchange (ETDEWEB)

Warren, C.C. [Nuclear Power Plants Operation Department, Slovenske Elektrarne, a.s., Mlynske nivy 47, 821 09 Bratislava (Slovakia)

2010-07-01

Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

Standard concerning the design of nuclear power stations in earthquake-prone districts

International Nuclear Information System (INIS)

Kirillov, A.P.; Anbriashivili, Y.K.; Suvilova, A.V.

1980-01-01

The measures of security assurance against the effect of radioactive contamination has become more and more complex due to the construction of nuclear power stations of diverse types. The aseismatic measures for the nuclear power stations built in the districts where earthquakes of different intensity occur are important problems. All main machinery and equipments and emergency systems in power stations must be protected from earthquakes, and this makes the solution of problems difficult. At present in USSR, the provisional standard concerning the design of atomic energy facilities built in earthquake-prone districts is completed. The basic philosophy of the standard is to decide the general requirements as the conditions for the design of nuclear power stations built in earthquake-prone districts. The lowest earthquake activity in the construction districts is considered as magnitude 4, and in the districts where earthquake activity is magnitude 9 or more, the construction of nuclear power stations is prohibited. Two levels of earthquake action are specified for the design: design earthquake and the largest design earthquake. The construction sites of nuclear power stations must be 15 to 150 km distant from the potential sources of earthquakes. Nuclear power stations are regarded as the aseismatically guaranteed type when the safety of reactors is secured under the application of the standard. The buildings and installations are classified into three classes regarding the aseismatic properties. (Kako, I.)

Technical supports for nuclear control

Energy Technology Data Exchange (ETDEWEB)

An, Jong Sung; Kwak, Eun Hoh; Noh, Sung Kee; Soh, Dong Sub; Yoon, Wan Kee; Shin, Jang Soo; Paek, Dae Hyun; Park, Wan Soo; Kim, Hyun Tae; Park, Chan Sik; Cha, Hong Yul; Choi, Yoon Dong; Park, Jin Hoh; Lee, Eui Jin; An, Jin Soo; Kim, Jong Heui [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-12-01

The project was carried out to support the establishment of the system of accountancy and control of nuclear materials in Korea. The training of inspectors and seminar were held to improve inspection capability of the nuclear inspectors. The information about the north Korean nuclear activities were successfully analyzed. In the drafts of nuclear energy law the national inspection and the regulation of physical protection were newly introduced for the purpose to clarify the openness of nuclear activities in Korea. 1 fig, 20 tabs, 19 refs. (Author).

Personnel involved in the development of nuclear standards in the United States, 1975

International Nuclear Information System (INIS)

Johnson, E.B.

1976-05-01

The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

Personnel involved in the development of nuclear standards in the United States, 1976

International Nuclear Information System (INIS)

Johnson, E.B.

1977-03-01

The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

Personnel involved in the development of nuclear standards in the United States, 1976

Energy Technology Data Exchange (ETDEWEB)

Johnson, E.B. (ed.)

1977-03-01

The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

Personnel involved in the development of nuclear standards in the United States, 1975

Energy Technology Data Exchange (ETDEWEB)

Johnson, E.B. (ed.)

1976-05-01

The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

Application of system dynamics on nuclear policy model

International Nuclear Information System (INIS)

An, N. S.; Kim, J. C.; Kim, D. W.; Kang, S. C.

2000-01-01

A system dynamics model for a nuclear energy policy in Korea (SIMNEP) was developed to analyze the Korea nuclear system and to predict the influence of the nuclear energy policy in the future. Two cases were analyzed using SIMNEP. The first case is to see the effect of the occurrence of severe nuclear accident in foreign country on the Korean government support. In the beginning, the Korean government support drops but jump up to the higher value than normal support due to the intelligentsia support influenced by the delay time of perception. Then, the national government support converges to the normal support. This turns out that the intelligentsia support plays a major role in increasing the government support. The second case is to see the effect of prior efforts on the foreign factors and/or on domestic factors on the U.S. government support. In the short term, effort on the U.S. government is more effective to increase U.S. government support but in the long term (about after 5 years), efforts on the domestic factors influence on the U.S. government support more than efforts on the foreign factors. The Korean government counter reaction among the influencing factors on the U.S. government support plays a major role to explain this result

Korean Variant Archive (KOVA): a reference database of genetic variations in the Korean population.

Science.gov (United States)

Lee, Sangmoon; Seo, Jihae; Park, Jinman; Nam, Jae-Yong; Choi, Ahyoung; Ignatius, Jason S; Bjornson, Robert D; Chae, Jong-Hee; Jang, In-Jin; Lee, Sanghyuk; Park, Woong-Yang; Baek, Daehyun; Choi, Murim

2017-06-27

Despite efforts to interrogate human genome variation through large-scale databases, systematic preference toward populations of Caucasian descendants has resulted in unintended reduction of power in studying non-Caucasians. Here we report a compilation of coding variants from 1,055 healthy Korean individuals (KOVA; Korean Variant Archive). The samples were sequenced to a mean depth of 75x, yielding 101 singleton variants per individual. Population genetics analysis demonstrates that the Korean population is a distinct ethnic group comparable to other discrete ethnic groups in Africa and Europe, providing a rationale for such independent genomic datasets. Indeed, KOVA conferred 22.8% increased variant filtering power in addition to Exome Aggregation Consortium (ExAC) when used on Korean exomes. Functional assessment of nonsynonymous variant supported the presence of purifying selection in Koreans. Analysis of copy number variants detected 5.2 deletions and 10.3 amplifications per individual with an increased fraction of novel variants among smaller and rarer copy number variable segments. We also report a list of germline variants that are associated with increased tumor susceptibility. This catalog can function as a critical addition to the pre-existing variant databases in pursuing genetic studies of Korean individuals.

Nuclear energy for the green development of Korea

International Nuclear Information System (INIS)

Jung, Young-Eek; Kim, Il-Dong; Lee, Sang-Don; Jeong, Young-Gi

2009-01-01

The Korean government announced the 'Basic Plan for National Energy towards 2030' last year. The goal of the plan is to achieve energy security, energy efficiency and environmental protection. To achieve green development Korean government plans to increase the portion of nuclear and renewable energy and reduce that of coal and oil energy. According to the plan, Korea will build another 9 units until 2030 and nuclear energy will represent 59% of electricity demands by 2030 which is about 20% higher than last year. Even though environment surrounding the nuclear industry is changing favorably and the government has a plan to increase nuclear energy for green development and optimal energy mix, we have to meet some challenges in the area of safety, waste disposal, public acceptance, and technology development. In this paper, we introduced the history, current status and future prospect of the nuclear industry in Korea, discussed new roles of nuclear energy, and made suggestions how to meet challenges and brace up for the global nuclear renaissance. (author)

ASME nuclear codes and standards: Recent technical initiatives

International Nuclear Information System (INIS)

Feigel, R. E.

1995-01-01

Although nuclear power construction is currently in a hiatus in the US, ASME and its volunteer committees remain committed to continual improvements in the technical requirements in its nuclear codes. This paper provides an overview of several significant recent revisions to ASME' s nuclear codes. Additionally, other important initiatives currently being addressed by ASME committees will be described. With the largest population of operating light water nuclear plants in the world and worldwide use of its nuclear codes, ASME continues to support technical advancements in its nuclear codes and standards. While revisions of various magnitude are an ongoing process, several recent revisions embody significant changes based on state of the art design philosophy and substantial industry experience. In the design area, a significant revisions has recently been approved which will significantly reduce conservatisms in seismic piping design as well as provide simplified design rules. Major revisions have also been made to the requirements for nuclear material manufacturers and suppliers, which should result in clearer understanding of this difficult administrative area of the code. In the area of Section XI inservice rules, substantial studies are underway to investigate the application of probabilistic, risked based inspection in lieu of the current deterministic inspection philosophy. While much work still is required in this area, it is an important potential application of the emerging field of risk based inspection

2014 Korean guidelines for appropriate utilization of cardiovascular magnetic resonance imaging: A joint report of the Korean Society of Cardiology and the Korean Society of Radiology

Energy Technology Data Exchange (ETDEWEB)

Yoon, Yeon Yee E. [Dept. of Cardiology, Cardiovascular Center, Seoul National University Bundang Hospital, Seoul (Korea, Republic of); Hong, Yoo Jin; Choi, Eui Young [Dept. of Radiology, Severance Hospital, Yonsei University College of Medicine, Seoul (Korea, Republic of); and others

2015-04-15

The use of cardiac magnetic resonance (CMR) imaging is increasing for the assessment of certain cardiovascular diseases, due to recent technical developments. CMR can give physicians information that cannot be found with other imaging modalities. However, there has been no guideline for the use of CMR in Korean people. Therefore, we have prepared a Korean guideline for the appropriate utilization of CMR to guide Korean physicians, imaging specialists, medical associates, and patients to improve the overall performances in medical system. By addressing CMR usage and creating these guidelines, we hope to contribute to the promotion of public health. This guideline is a joint report of the Korean Society of Cardiology and the Korean Society of Radiology.

2014 Korean Guidelines for Appropriate Utilization of Cardiovascular Magnetic Resonance Imaging: A Joint Report of the Korean Society of Cardiology and the Korean Society of Radiology

Energy Technology Data Exchange (ETDEWEB)

Yoon, Yeonyee E. [Department of Cardiology, Cardiovascular Center, Seoul National University Bundang Hospital, Seongnam 463-707 (Korea, Republic of); Hong, Yoo Jin [Department of Radiology, Severance Hospital, Yonsei University College of Medicine, Seoul 120-752 (Korea, Republic of); Kim, Hyung-Kwan [Division of Cardiology, Department of Internal Medicine, Cardiovascular Center, Seoul National University College of Medicine, Seoul National University Hospital, Seoul 110-744 (Korea, Republic of); Kim, Jeong A [Department of Radiology, Ilsan Paik Hospital, Inje University College of Medicine, Goyang 411-706 (Korea, Republic of); Na, Jin Oh [Cardiovascular Center, Korea University Guro Hospital, Korea University College of Medicine, Seoul 152-703 (Korea, Republic of); Yang, Dong Hyun [Department of Radiology, Asan Medical Center, University of Ulsan College of Medicine, Seoul 138-736 (Korea, Republic of); Kim, Young Jin [Department of Radiology, Severance Hospital, Yonsei University College of Medicine, Seoul 120-752 (Korea, Republic of); Choi, Eui-Young [Division of Cardiology, Gangnam Severance Hospital, Yonsei University College of Medicine, Seoul 135-720 (Korea, Republic of)

2014-07-01

Cardiac magnetic resonance (CMR) imaging is now widely used in several fields of cardiovascular disease assessment due to recent technical developments. CMR can give physicians information that cannot be found with other imaging modalities. However, there is no guideline which is suitable for Korean people for the use of CMR. Therefore, we have prepared a Korean guideline for the appropriate utilization of CMR to guide Korean physicians, imaging specialists, medical associates and patients to improve the overall medical system performances. By addressing CMR usage and creating these guidelines we hope to contribute towards the promotion of public health. This guideline is a joint report of the Korean Society of Cardiology and the Korean Society of Radiology.

2014 Korean guidelines for appropriate utilization of cardiovascular magnetic resonance imaging: A joint report of the Korean Society of Cardiology and the Korean Society of Radiology

International Nuclear Information System (INIS)

Yoon, Yeon Yee E.; Hong, Yoo Jin; Choi, Eui Young

2015-01-01

The use of cardiac magnetic resonance (CMR) imaging is increasing for the assessment of certain cardiovascular diseases, due to recent technical developments. CMR can give physicians information that cannot be found with other imaging modalities. However, there has been no guideline for the use of CMR in Korean people. Therefore, we have prepared a Korean guideline for the appropriate utilization of CMR to guide Korean physicians, imaging specialists, medical associates, and patients to improve the overall performances in medical system. By addressing CMR usage and creating these guidelines, we hope to contribute to the promotion of public health. This guideline is a joint report of the Korean Society of Cardiology and the Korean Society of Radiology.

An anthropometric analysis of Korean male helicopter pilots for helicopter cockpit design.

Science.gov (United States)

Lee, Wonsup; Jung, Kihyo; Jeong, Jeongrim; Park, Jangwoon; Cho, Jayoung; Kim, Heeeun; Park, Seikwon; You, Heecheon

2013-01-01

This study measured 21 anthropometric dimensions (ADs) of 94 Korean male helicopter pilots in their 20s to 40s and compared them with corresponding measurements of Korean male civilians and the US Army male personnel. The ADs and the sample size of the anthropometric survey were determined by a four-step process: (1) selection of ADs related to helicopter cockpit design, (2) evaluation of the importance of each AD, (3) calculation of required sample sizes for selected precision levels and (4) determination of an appropriate sample size by considering both the AD importance evaluation results and the sample size requirements. The anthropometric comparison reveals that the Korean helicopter pilots are larger (ratio of means = 1.01-1.08) and less dispersed (ratio of standard deviations = 0.71-0.93) than the Korean male civilians and that they are shorter in stature (0.99), have shorter upper limbs (0.89-0.96) and lower limbs (0.93-0.97), but are taller on sitting height, sitting eye height and acromial height (1.01-1.03), and less dispersed (0.68-0.97) than the US Army personnel. The anthropometric characteristics of Korean male helicopter pilots were compared with those of Korean male civilians and US Army male personnel. The sample size determination process and the anthropometric comparison results presented in this study are useful to design an anthropometric survey and a helicopter cockpit layout, respectively.

Status of ANSI standards on decommissioning of nuclear reprocessing facilities

International Nuclear Information System (INIS)

Graham, H.B.

1975-01-01

A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

Development of a standard equipment management model for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2012-10-15

Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed.

Development of a standard equipment management model for nuclear power plants

International Nuclear Information System (INIS)

Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun

2012-01-01

Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed

Development of standard testing methods for nuclear-waste forms

International Nuclear Information System (INIS)

Mendel, J.E.; Nelson, R.D.

1981-11-01

Standard test methods for waste package component development and design, safety analyses, and licensing are being developed for the Nuclear Waste Materials Handbook. This paper describes mainly the testing methods for obtaining waste form materials data

Standardized safety management of AP1000 nuclear power plant

International Nuclear Information System (INIS)

Li Xingwen; Cao Zhiqiang; Cong Jiuyuan

2011-01-01

In 2002, China published and implemented the Law of the People's Republic of China on Work Safety and promulgated a series of guidelines and policies, which strengthened the safety management supervision. Standardization of safety, as another important step on safety supervision, comes after safety assesment and safety production licensing system, is also a permanent solution. Standardization of safety is a strategic, long term and fundamental work, which is also the basic access to achieving scientific safety management and increasing the inherent safety of an enterprise. Haiyang AP1000 nuclear power plant, adopting the modularized, 'open-top' and parallel construction means, overturned the traditional construction theory of installation work comes after the civil work and greatly shorten the construction period. At the same time, the notable increase of oversize module transportation and lifting and parallel construction raises higher demands for safety management. This article combines the characteristics and difficulties of safety management for Haiyang AP1000 nuclear power plant, puts forward ideas and methods for standardized safety management, and could also serve as reference to the safety management for other AP1000 projects. (authors)

Fourteen lessons learned from the successful nuclear power program of the Republic of Korea

International Nuclear Information System (INIS)

Choi, Sungyeol; Jun, Eunju; Hwang, IlSoon; Starz, Anne; Mazour, Tom; Chang, SoonHeung; Burkart, Alex R.

2009-01-01

This paper summarized a development history and lessons of Korean nuclear power infrastructures from the beginning of the nuclear power program in 1956 to the localization of complete scope of PWR technology in 1990. The objective of this paper is to show the guideline on the issues that the development of a national infrastructure for nuclear power using the realistic experiences in order to help the developing countries newly starting nuclear power program as a long-term energy supply option. Development strategies and lessons learned from the successful Korean experience have been presented based on milestones structure of IAEA in order to help decision makers, advisers, senior managers and national planners of nuclear power program. Lessons for national nuclear power programs include considerations before launching a program, preparation and decision making, and the construction of the first nuclear power plant. Scope of these lessons includes knowledge and human resources management, financial and industrial infrastructure development, nuclear safety, legislative and regulatory experiences, fuel cycle and waste management, international cooperation. Fourteen lessons learned either positive or not are derived from the Korean case and are suggested for incorporation in the IAEA's efforts in support of developing countries' development of nuclear infrastructure and planning.

Preliminary investigation study of code of developed country for developing Korean fuel cycle code

International Nuclear Information System (INIS)

Jeong, Chang Joon; Ko, Won Il; Lee, Ho Hee; Cho, Dong Keun; Park, Chang Je

2012-01-01

In order to develop Korean fuel cycle code, the analyses has been performed with the fuel cycle codes which are used in advanced country. Also, recommendations were proposed for future development. The fuel cycle codes are AS FLOOWS: VISTA which has been developed by IAEA, DANESS code which developed by ANL and LISTO, and VISION developed by INL for the Advanced Fuel Cycle Initiative (AFCI) system analysis. The recommended items were proposed for software, program scheme, material flow model, isotope decay model, environmental impact analysis model, and economics analysis model. The described things will be used for development of Korean nuclear fuel cycle code in future

Update to nuclear data standards for nuclear measurements. Summary report of a consultants` meeting

Energy Technology Data Exchange (ETDEWEB)

Wienke, H. [ed.; International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section; Carlson, A. D. [National Inst. of Standards and Technology, Gaithersburg, MD (United States); Chiba, S. [Japan Atomic Energy Research Inst., Tokai (Japan); Hambsch, F. J. [Institute for Reference Materials and Measurements, Geel (Belgium); Olsson, N. [Department of Neutron Research, Uppsala Univ., Uppsala (Sweden); Smirnov, A. N. [V.G. Khlopin Radium Inst., St. Petersburg (Russian Federation)

1997-05-01

This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the {sup 10}B(n,{alpha}) reaction in the energy region below 20 Mev; and the H(n,n), {sup 235}U9(n,f), {sup 238}U(n,f), and {sup 209}Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs.

Measurement of the internal organs' absorption and extracorporeal excretion of radioactive iodine fit to the characteristics of Koreans

International Nuclear Information System (INIS)

Kim, Jung Hoon; Kim, Tae Man; Whang, Joo Ho

2005-01-01

Radiation dosimetry will prove helpful to active approaches, such as limiting the amount of radiation exposure, which can be called the negative effect of radiation on the body, or using radiation to treat diseases. Defective nuclear fuel at a nuclear power plant or 131 I used for oral thyroid gland examination and treatment of cancer may cause internal exposure during the replacement of nuclear fuel, or maintenance. Also, it is reported that, clinically, 131 I has the negative function of increasing the radiation exposure of the other organs as well as the positive function related to thyroid gland diagnosis and cancer treatment. Estimation of internal exposure to 131 I must take the physical properties of 131 I and the physiological properties of individuals into account. The extracorporeal excretion rate of radionuclides and the proportion remaining in the body may vary depending on the physiological properties of the Oriental and Occidental people. The existing physiological properties are data originating from Westerners, so if the data are applied to Koreans, differences in dietary life and physiological properties may lead to underestimation or overestimation of internal exposure. Therefore, this study aims at measuring the radionuclide absorption and excretion rates in human organs to establish the physiological radionuclide metabolism fit to Koreans and the Oriental people whose physique is similar to that of Koreans

Licensing procedure, nuclear codes and standards in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schultheiss, G.F.

1980-01-01

The present paper deals with legal background of licensing in nuclear technology and atomic energy use, licensing procedures for nuclear power plants and with codes, standards and guidelines in the Federal Republic of Germany. (orig./RW)

North Korean refugee doctors' preliminary examination scores

Directory of Open Access Journals (Sweden)

Sung Uk Chae

2016-12-01

Full Text Available Purpose Although there have been studies emphasizing the re-education of North Korean (NK doctors for post-unification of the Korean Peninsula, study on the content and scope of such re-education has yet to be conducted. Researchers intended to set the content and scope of re-education by a comparative analysis for the scores of the preliminary examination, which is comparable to the Korean Medical Licensing Examination (KMLE. Methods The scores of the first and second preliminary exams were analyzed by subject using the Wilcoxon signed rank test. The passing status of the group of NK doctors for KMLE in recent 3 years were investigated. The multiple-choice-question (MCQ items of which difficulty indexes of NK doctors were lower than those of South Korean (SK medical students by two times of the standard deviation of the scores of SK medical students were selected to investigate the relevant reasons. Results The average scores of nearly all subjects were improved in the second exam compared with the first exam. The passing rate of the group of NK doctors was 75%. The number of MCQ items of which difficulty indexes of NK doctors were lower than those of SK medical students was 51 (6.38%. NK doctors’ lack of understandings for Diagnostic Techniques and Procedures, Therapeutics, Prenatal Care, and Managed Care Programs was suggested as the possible reason. Conclusion The education of integrated courses focusing on Diagnostic Techniques and Procedures and Therapeutics, and apprenticeship-style training for clinical practice of core subjects are needed. Special lectures on the Preventive Medicine are likely to be required also.

American National Standard: nuclear data sets for reactor design calculations

International Nuclear Information System (INIS)

1983-01-01

This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include criteria for acceptance of evaluated nuclear data sets, criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

A study on the development of national guide for implementing nuclear security culture in ROK

Energy Technology Data Exchange (ETDEWEB)

Koh, Moonsung; Lee, Youngwook; Yoo, Hosik [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2014-05-15

Among the extended concepts, a remarkable thing is that nuclear security began to be focused on the human factor as well as technical factors (hardware and software system) because most security lapses at nuclear power facilities result from human failings such as low motivation, miscalculation, or malice. Nuclear Security Culture (NSC) is designed to improve the performance of the human factor and to make its interface with security technology and regulations more effective and smooth. There is a need to develop a variety of more efficient tools for achieving sustainable nuclear security culture. We studied for the implementing guide to establish and enhance the nuclear security culture. We have developed the Nuclear Security Culture Implementing Guidelines for licensees in order to enhance nuclear security culture. Licensees have separately established a separate code of conduct on nuclear security culture for their daily business based on such Implementing Guidelines. The Nuclear Security Culture Implementing Guidelines were developed with sufficient consideration of both the IAEA Security Series on nuclear security culture and the Korean circumstances. In all, the Korean government and licensees have timely established and applied the Implementing Guidelines and code of conduct and consequently paved the way for further improvements of the Korean nuclear security regime. The nuclear security culture will facilitate and optimize the human aspects in our nuclear security programs.

A study on the development of national guide for implementing nuclear security culture in ROK

International Nuclear Information System (INIS)

Koh, Moonsung; Lee, Youngwook; Yoo, Hosik

2014-01-01

Among the extended concepts, a remarkable thing is that nuclear security began to be focused on the human factor as well as technical factors (hardware and software system) because most security lapses at nuclear power facilities result from human failings such as low motivation, miscalculation, or malice. Nuclear Security Culture (NSC) is designed to improve the performance of the human factor and to make its interface with security technology and regulations more effective and smooth. There is a need to develop a variety of more efficient tools for achieving sustainable nuclear security culture. We studied for the implementing guide to establish and enhance the nuclear security culture. We have developed the Nuclear Security Culture Implementing Guidelines for licensees in order to enhance nuclear security culture. Licensees have separately established a separate code of conduct on nuclear security culture for their daily business based on such Implementing Guidelines. The Nuclear Security Culture Implementing Guidelines were developed with sufficient consideration of both the IAEA Security Series on nuclear security culture and the Korean circumstances. In all, the Korean government and licensees have timely established and applied the Implementing Guidelines and code of conduct and consequently paved the way for further improvements of the Korean nuclear security regime. The nuclear security culture will facilitate and optimize the human aspects in our nuclear security programs

Round table discussion: Quality control and standardization of nuclear medicine software

International Nuclear Information System (INIS)

Anon.

1988-01-01

In summary the round table came to the following important conclusions: Nuclear medicine software systems need better documentation, especially regarding details of algorithms and limitations, and user friendliness could be considerably improved. Quality control of software is an integral part of quality assurance in nuclear medicine and should be performed at all levels of the software. Quality control of applications software should preferably be performed with assistance of generally accepted software phantoms. A basic form of standardization was welcomed and partly regarded as essential by all participants. Some areas such as patient study files could be standardized in the near future, whereas other areas such as the standardization of clinical applications programs or acquisition protocols still present major difficulties. An international cooperation in the field of standardization of software and other topics has already been started on the European level and should be continued and supported. (orig.)

Standard rules for liability and cover for nuclear installations

International Nuclear Information System (INIS)

Pfaffelhuber, J.K.; Kuckuck, B.

1980-01-01

To afford full protection for possible victims, the authors of this article are in favour of doing away with the limitation of liability of nuclear operators presently provided under the German Atomic Energy Act, the principle of which is based on the Paris Convention and the Brussels Supplementary Convention. In support of this argument reference is made to the recent accident at Three Mile Island, trends in other national legislation towards unlimited liability as well as high safety standards in German nuclear plants. Finally, possible ways of providing unlimited liability are proposed, in particular increased insurance cover and the constitution of an interest-bearing fund in addition to State intervention in case of a major nuclear incident. (NEA) [fr

An application of the IAEA GCS-R-3 Standard in Nuclear Quality Management System

Energy Technology Data Exchange (ETDEWEB)

Kim, D. I.; Juhn, P. E. [TUEV SUED Korea, Seoul (Korea, Republic of); Kwon, M. J. [TUEV SUED KOCEN, Seoul (Korea, Republic of)

2012-03-15

IAEA GCS-R-3 Standard (2006) is intended to help nuclear community establishing a nuclear quality management system that integrates such 6 elements as safety, health, environment, security, quality and economics. In the present paper, the management principles of GCS-R-3 Standard are compared with those of ISO 9001 and ASME N/A-1 Codes and Standards. The paper also summarizes the worldwide survey on application of GS-R-3, which was conducted by the TUEV SUED Korea in 2011. The result concludes that the top priority should be given to safety upon which the management system must be based, in proper coordination with other 5 elements to enhance nuclear safety, in particular after Fukushima Dais-Ici nuclear power accidents on 11{sup th} March 2011 in Japan.

Contribution of the C.E.A. to standardization of nuclear plant equipments

International Nuclear Information System (INIS)

Dumax, P.; Seran, R.

1980-01-01

In research and production laboratories working in the nuclear field standardization of equipments greatly improves the profits of the installation and the protection of individuals and goods. The standardization effort on technical equipments of shielding, handling, detection and safety (so called P.M.D.S.) initiated by the C.E.A. in 1967 is being carried out now within the Institute of Protection and Nuclear Safety (I.P.S.N.) by a technical Service specialized in protection and dosimetry (S.T.E.P.D.). Its purpose is to establish standardization documents for internal use and to take part in the work of official standardization organizations. The benefits of standardization are reviewed. The achievements of the various working groups common to C.E.A. centers are stated and the documents published or to be published are listed [fr